WorldWideScience

Sample records for selection qualification requirements

  1. 5 CFR 330.208 - Qualification requirements.

    Science.gov (United States)

    2010-01-01

    ... perform the duties and responsibilities of the position. (c) The sex of an individual may not be... qualified for a position if he or she: (1) Meets OPM-established or approved qualification standards and requirements for the position, including any minimum educational requirements, and any selection placement...

  2. Sport Management Interns--Selection Qualifications.

    Science.gov (United States)

    Cuneen, Jacquelyn; Sidwell, M. Joy

    1993-01-01

    Examines and rates the background qualifications and qualities, identified by sport management practitioners through an examination of paper credentials, that are desired in interviewees vying for selection into sport management internship positions. (GLR)

  3. Selection of equipment for equipment qualification

    International Nuclear Information System (INIS)

    Torr, K.G.

    1989-01-01

    This report describes the methodology applied in selecting equipment in the special safety systems for equipment qualification in the CANDU 600 MW nuclear generating stations at Gentilly 2 and Point Lepreau. Included is an explanation of the selection procedure adopted and the rationale behind the criteria used in identifying the equipment. The equipment items on the list have been grouped into three priority categories as a planning aid to AECB staff for a review of the qualification status of the special safety systems

  4. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Culbert, W.H.

    1985-10-01

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.

  5. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Culbert, W.H.

    1985-10-01

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit

  6. Software qualification of selected TOUGH2 modules

    International Nuclear Information System (INIS)

    Wu, Y.S.; Ahlers, C.F.; Fraser, P.; Simmons, A.; Pruess, K.

    1996-10-01

    The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of the single-phase Gas (EOS1G), Effective Continuum Method (ECM), Saturated/Unsaturated Flow (EOS9), and Radionuclide Transport (T2R3D) modules of TOUGH2, a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. This report contains the following sections: (1) Requirements Specification, (2) Design Description, (3) Software Validation Test Plan and Report, (4) Software User Documentation, and (5) Appendices. These sections comprise sequential parts of the Software Life Cycle, and are not intended to stand alone but should be used in conjunction with the TOUGH User's Guide (Pruess, 1987), TOUGH2--A General Purpose Numerical Simulator for Multiphase Fluid and Heat Flow (Pruess, 1991), and the above-referenced TOUGH2 software qualification document. The qualification package is complete with the attached Software Identification Form and executable source code for the single-phase Gas, Effective Continuum method, Saturated/Unsaturated Flow, and Radionuclide Transport modules of TOUGH2

  7. INDUSTRIAL RESTRUCTURING AND PROFESSIONAL QUALIFICATION REQUIREMENTS

    Directory of Open Access Journals (Sweden)

    João Amato Neto

    2014-09-01

    Full Text Available Among the most complex subjects that affect modern society in this early millennium, the problem of relationships between the educational patterns and the work organization seems to be one of the most important and full of uncertainties. Specially, this problem acquires greater relevance when one thinks of the impacts of the techno-scientific revolution in the work world, as well as in the educational system. In this sense, the present work researches some elements regarding the new educational patterns and qualification requirements in face of the new industrial paradigm and discusses the transformations accomplished by the techno-scientific revolution and its implications on the new lean and flexible production paradigm and on the (reorganization of work in the modern industry. The methodological approach is based on a bibliographic revision with a quantitative approach.

  8. 14 CFR 121.437 - Pilot qualification: Certificates required.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Certificates required... Pilot qualification: Certificates required. (a) No pilot may act as pilot in command of an aircraft (or... pilots) unless he holds an airline transport pilot certificate and an appropriate type rating for that...

  9. 48 CFR 1437.7001 - Contractor qualification requirements.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Contractor qualification requirements. 1437.7001 Section 1437.7001 Federal Acquisition Regulations System DEPARTMENT OF THE INTERIOR... Contractor qualification requirements. (a) Prior to award of a contract for real property appraisal services...

  10. Selection, qualification and training of personnel for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This standard provides criteria for the selection, qualification and training of personnel for stationary nuclear power plants. Qualifications, responsibilities, and training of personnel in operating and support organizations appropriate for the safe and efficient operation of nuclear power plants are addressed

  11. Evaluation and qualification of novel control techniques with safety requirements

    International Nuclear Information System (INIS)

    Gossner, S.; Wach, D.

    1985-01-01

    The paper discusses the questions related to the assessment and qualification of new I and C-systems. The tasks of nuclear power plant I and Cs as well as the efficiency of the new techniques are reflected. Problems with application of new I and Cs and the state of application in Germany and abroad are addressed. Starting from the essential differencies between conventional and new I and C-systems it is evaluated, if and in which way existing safety requirements can be met and to what extent new requirements need to be formulated. An overall concept has to be developed comprising the definition of graded requirement profiles for design and qualification. Associated qualification procedures and tools have to be adapted, developed and tuned upon each other. (orig./HP) [de

  12. 21 CFR 111.12 - What personnel qualification requirements apply?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false What personnel qualification requirements apply? 111.12 Section 111.12 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) FOOD FOR HUMAN CONSUMPTION CURRENT GOOD MANUFACTURING PRACTICE IN MANUFACTURING...

  13. Developing, Approving and Maintaining Qualifications: Selected International Approaches. Research Report

    Science.gov (United States)

    Misko, Josie

    2015-01-01

    There are lessons for Australia in the key approaches to the development, approval, maintenance and quality assurance of qualifications adopted in countries overseas. This research takes into account a range of approaches used in selected European Union (EU) member states (Germany, Finland and Sweden), the United Kingdom (England, Northern Ireland…

  14. 78 FR 53025 - Pilot Certification and Qualification Requirements for Air Carrier Operations; Correction

    Science.gov (United States)

    2013-08-28

    ...-0100; Amdt. No. 141-17A] RIN 2120-AJ67 Pilot Certification and Qualification Requirements for Air... regulations to create new certification and qualification requirements for pilots in air carrier operations..., the FAA published a final rule entitled, ``Pilot Certification and Qualification Requirements for Air...

  15. Selection of operations staff, qualifications and experience

    International Nuclear Information System (INIS)

    Gutmann, H.

    1977-01-01

    Requirements and suggestions have been made by authorities and various organisations in a number of countries which define necessary experience and training for the various groups of nuclear power plant personnel. For two countries, the USA and the FRG, a comparison has been made which shows that there is only a slight deviation, taking into account the different education systems. With the example of the Biblis nuclear power plant the training on the job is described. Especially the production or operation department is looked at in more detail. The training is split up into several parts: a general part, such as nuclear physics, reactor physics and engineering, reactor safety, radiation protection and so on and a plant related part, such as arrangement and mode of operation of the plant under normal and accident conditions, license conditions and so on. (orig.) [de

  16. Qualification Requirements for Foreign Suppliers in Public Procurement – Evidence from the Czech Republic

    Directory of Open Access Journals (Sweden)

    Vyklický Martin

    2016-03-01

    Full Text Available Qualification requirements for foreign suppliers in Public Procurement (PP are quite different in each European Union (EU member state. The most complex requirements for foreign suppliers in the context of public purchases are included in the Czech PP law. The aim of this paper is to make an overview of the problem of qualification requirements for foreign suppliers in the PP law of the CR. Its sub-objectives are the identification and explanation of solutions to the problem in the PP legislation of neighboring countries of the CR that are also members of the EU. The methodological part of the contribution is based mainly on the analysis and critical evaluation of the current state of legal issues relating to the proof of qualification of foreign suppliers in PP orders of the CR; with examples of fairly extensive decision-making practices of the Office for the Protection of Competition and law courts, including the jurisprudence of the European Court of Justice. The paper highlights the unnecessary complexity of qualification requirements that, on purely formal grounds, inhibits submissions of tenders from potential foreign suppliers that would otherwise be able to submit a bid for a public contract without any problems whatsoever. The authors are using and applying a comparative-legal method in the context of the comparison of the PP legislation of neighboring countries of the CR that are also members of the EU. The case study of foreign suppliers bidding for above-threshold public tenders in the CR at the minimum legal requirements of the contracting authority (CA for proof of qualification, the comparation study with selected EU countries or analysis of the development of the proportion of public contracts awarded to foreign suppliers in 2010–2014 shows that there is legislation uncertainty in EU PP law that should be reduced and simplified on an EC basis.

  17. Significance of ITER IWS Material Selection and Qualification

    Science.gov (United States)

    Mehta, Bhoomi K.; Raval, Jigar; Maheshwari, Abha; Laad, Rahul; Singh, Gurlovleen; Pathak, Haresh

    2017-04-01

    In-Wall Shielding (IWS) is one of the important components of ITER Vacuum Vessel (VV) which fills the space between double walls of VV with cooling water. Procurement Arrangement (PA) for IWS has been signed with Indian Domestic Agency (INDA). Procurement of IWS materials, fabrication of IWS blocks and its delivery to respective Domestic Agency (DA) and ITER Organization (IO) are the main scope of this PA. Hence, INDIA is the only country which is contributing to VV IWS among all seven ITER partners. The main functions of the IWS are to provide Neutron Shielding with blanket, VV shells and water during plasma operations and to reduce ripple of the Toroidal Magnetic Field. To meet these functional requirements IWS blocks are made up of special materials (Borated Steels SS304 B4 & SS304 B7, Ferritic Steels SS 430, Austenitic Steel SS 316 L (N)-IG, XM-19 and Inconel-625) which are qualified, reliable and traceable for the design assessment. The choice of these materials has a significant influence on performance, maintainability, licensing, detailed design parameters and waste disposal. The main reasons for the materials selected for IWS are its high mechanical strength at operating temperatures, water chemistry properties, excellent fabrication characteristics and low cost relative to other similar materials. All the materials are qualified with respect to their respective codes (ASTM/EN standards with additional requirements as described in RCC-MR code 2007) and ITER requirements. Agreed Notified Body (ANB) has control conformity of materials certificates with approved material specification and traceability procedure for Safety Important Component (SIC). The procurement strategy for all the IWS materials has been developed in close collaboration with IO, ANB and Industries as per Product Procurement Specification (PPS). The R&D for sample, bulk material production, testing, inspection and handling as required are carried out by IN DA and IO. At present almost all

  18. Decree of the State Office for Nuclear Safety No. 146/1997 of 18 June 1997 specifying activities which have an immediate impact on nuclear safety, and activities which are particularly important with respect to radiation protection, requirements for qualification and professional training, procedures for examining special professional competence and for granting certificates to selected personnel, and the scope and structure of documentation to be approved for permitting the training of selected personnel

    International Nuclear Information System (INIS)

    1997-01-01

    The Decree specifies requirements in the following fields: (a) activities which have an immediate impact on nuclear safety and activities which are particularly important with respect to radiation protection; (b) requirements for the qualification of selected personnel; (c) requirements for professional training of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources who are to gain special professional competence; (d) examination commission; (e) examination of special professional competence of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources; (f) granting permission to perform activities of selected personnel; and (g) scope and structure of documentation required to permit professional training of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources. (P.A.)

  19. Understanding to requirements for educational level in qualification of reactor operators

    International Nuclear Information System (INIS)

    Zhang Chi; Yang Di; Zhou Limin

    2007-01-01

    Requirements for qualification of reactor operators in nuclear safety regulations were discussed in this paper. The new issue was described in the confirmation of education level of reactor operators. The understanding to the requirements for Educational Level in Qualification of Reactor Operators was provided according to Higher Education Law of the People's Republic of China. It was proposed to improve the confirmation of qualification of reactor operators as soon as possible. (authors)

  20. 78 FR 44873 - Pilot Certification and Qualification Requirements for Air Carrier Operations; Correction

    Science.gov (United States)

    2013-07-25

    ...-0100; Amdt. Nos. 61-130A] RIN 2120-AJ67 Pilot Certification and Qualification Requirements for Air... to create new certification and qualification requirements for pilots in air carrier operations. This... . SUPPLEMENTARY INFORMATION: Background On July 15, 2013, the FAA published a final rule entitled, ``Pilot...

  1. The qualification requirements for personnel carry out the testing for the pressure equipment materials

    International Nuclear Information System (INIS)

    Wojas, M.; Walczak, M.

    2006-01-01

    The article contains information about qualification requirements for personnel carry out the destructive and non-destructive testing for the pressure equipment materials based on the Directive 97/23/CE(PED). Competence laboratory carry out the testing. The responsibility lies with producer / employer. The producer / employer could elaborate the written practice procedure for qualification and certification testing personnel. (authors)

  2. Design requirements, criteria and methods for seismic qualification of CANDU power plants

    International Nuclear Information System (INIS)

    Singh, N.; Duff, C.G.

    1979-10-01

    This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)

  3. Establishment of an unrelated umbilical cord blood bank qualification program: ensuring quality while meeting Food and Drug Administration vendor qualification requirements.

    Science.gov (United States)

    Rabe, Fran; Kadidlo, Diane; Van Orsow, Lisa; McKenna, David

    2013-10-01

    Qualification of a cord blood bank (CBB) is a complex process that includes evaluation of multiple aspects of donor screening and testing, processing, accreditation and approval by professional cell therapy groups, and results of received cord blood units. The University of Minnesota Medical Center Cell Therapy Laboratory has established a CBB vendor qualification process to ensure the CBB meets established regulatory and quality requirements. The deployed qualification of CBBs is based on retrospective and prospective review of the CBB. Forty-one CBBs were evaluated retrospectively: seven CBBs were disqualified based on failed quality control (QC) results. Eight CBBs did not meet the criteria for retrospective qualification because fewer than 3 cord blood units were received and the CBB was not accredited. As of March 2012, three US and one non-US CBBs have been qualified prospectively. One CBB withdrew from the qualification process after successful completion of the comprehensive survey and subsequent failure of the provided QC unit to pass the minimum criteria. One CBB failed the prospective qualification process based on processing methods that were revealed during the paper portion of the evaluation. A CBB qualification process is necessary for a transplant center to manage the qualification of the large number of CBBs needed to support a umbilical cord blood transplantation program. A transplant center that has utilized cord blood for a number of years before implementation of a qualification process should use a retrospective qualification process along with a prospective process. © 2013 American Association of Blood Banks.

  4. The recertification of the professional accounting qualification in Estonia: the requirements and quality of CPD

    Directory of Open Access Journals (Sweden)

    Kaidi Kallaste

    2017-09-01

    Full Text Available The recertification of the professional accounting qualification in Estonia: the requirements and quality of CPD As the purpose of a professional qualification should be to ensure quality to employers/customers, appro-priate requirements for professional training should not be too low. On the other hand, too high require-ments for the amount of training would lead to the situation where maintaining the level is expensive and if the labour market does not consider having a professional certificate necessary, recertification will be discarded. The purpose of the research was to identify the factors that influence an accountant’s decision whether to recertify his/her professional qualification or not. The conditions of recertification were ana-lysed and compared to other countries as were the requirements set up for auditors. The results of the survey revealed that in Estonia the decision not to recertify one’s professional qualification was mainly due to not having fulfilled the required number of qualification hours or not having certificates proving one’s participation in qualification training sessions. At the same time, compared to other countries, the requirements in Estonia are very low. So that the increase in the amount of training would not hinder recertification, alternative solutions for Estonia are proposed in the article.

  5. Development of equipment qualification requirements for NPP instrumentation and control systems

    International Nuclear Information System (INIS)

    Siora, A. A.; Reshetitskij, S. V.; Harybin, A. V.

    2012-01-01

    The main stages of equipment qualification are presented. The aim of the work is to ensure compatibility between Ukrainian and international requirements. A comparison with US NRC requirements has been done. The approach in equipment qualification is presented for the resistance to: irradiation; dust; seismic motion, vibrations and mechanical impact; environmental impact (temperature, humidity, pressure); power supply parameters etc., as well as the technological testing

  6. Development of Regulatory Requirements for Qualification Management of Railway Drivers

    Energy Technology Data Exchange (ETDEWEB)

    Byun, Seong Nam; Kim, Sa Kil; Kyung, Tae Won; Kim, Jung Ho; Heo, Eun Mee; Park, Hong Jun [Kyung Hee University, Seoul (Korea, Republic of)

    2008-03-15

    It has been estimated that up to 90% of all workplace accidents have human error as a cause. Human error has been widely recognized as a key factor in almost all the highly publicized accidents, including Daegu subway fire of February 18, 2003 killed 198 people and injured 147. Because most human behavior is {sup u}nintentional{sup ,} carried out automatically, uncontrolled qualifications of rail drivers as root causes of human error should be carefully investigated and regulated by a legal authority.

  7. Development of Regulatory Requirements for Qualification Management of Railway Drivers

    International Nuclear Information System (INIS)

    Byun, Seong Nam; Kim, Sa Kil; Kyung, Tae Won; Kim, Jung Ho; Heo, Eun Mee; Park, Hong Jun

    2008-03-01

    It has been estimated that up to 90% of all workplace accidents have human error as a cause. Human error has been widely recognized as a key factor in almost all the highly publicized accidents, including Daegu subway fire of February 18, 2003 killed 198 people and injured 147. Because most human behavior is u nintentional , carried out automatically, uncontrolled qualifications of rail drivers as root causes of human error should be carefully investigated and regulated by a legal authority

  8. Guide to good practices for the selection, training, and qualification of shift technical advisors

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-01

    The DOE Guide to Good Practices For The Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor position. DOE Order 5480-20, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities,`` states that only Category A reactors must use shift technical advisor position. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is presented based on the premise that the trainee has not completed any facility-specific training other than general employee training.

  9. Safety at work due to staff qualification and selection

    International Nuclear Information System (INIS)

    Brandt, W.

    1980-01-01

    An outline of basic requirements enabling the selection of employees for responsible staff in nuclear power stations. Illustrated further by the example of a model development from skilled worker to head of shift. A short reference will be made to the maintenance of high standards of training. (orig.) [de

  10. Requirements for qualification of manufacture of the ITER Central Solenoid and Correction Coils

    Energy Technology Data Exchange (ETDEWEB)

    Libeyre, Paul, E-mail: paul.libeyre@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Li, Hongwei [ITER China, 15B Fuxing Road, Beijing 100862 (China); Reiersen, Wayne [US ITER Project Office, 1055 Commerce Park Dr., Oak Ridge, TN 37831 (United States); Dolgetta, Nello; Jong, Cornelis; Lyraud, Charles; Mitchell, Neil; Laurenti, Adamo [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Sgobba, Stefano [CERN, CH-1211 Genève 23 (Switzerland); Turck, Bernard [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Martovetsky, Nicolai; Everitt, David; Freudenberg, K.; Litherland, Steve; Rosenblad, Peter [US ITER Project Office, 1055 Commerce Park Dr., Oak Ridge, TN 37831 (United States); Smith, John; Spitzer, Jeff [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Wei, Jing; Dong, Xiaoyu; Fang, Chao [ASIPP, Shushan Hu Road 350, Hefei, Anhui 230031 (China); and others

    2015-10-15

    Highlights: • A manufacturing line is installed for the ITER Correction Coils. • A manufacturing line is under installation for the ITER Central Solenoid. • Qualification of the manufacturing procedures has started for both manufacturing lines and acceptance criteria set. • Winding procedure of Correction Coils is qualified. - Abstract: The manufacturing line of the ITER Correction Coils (CC) at ASIPP in Hefei (China) was completed in 2013 and the manufacturing line of the ITER Central Solenoid (CS) modules is under installation at General Atomic premises in Poway (USA). In both cases, before starting production of the first coils, qualification of the manufacturing procedures is achieved by the construction of a set of mock-ups and prototypes to demonstrate that design requirements defined by the ITER Organization are effectively met. For each qualification item, the corresponding mock-ups are presented with the tests to be performed and the related acceptance criteria. The first qualification results are discussed.

  11. Standard guide for the selection, training and qualification of nondestructive assay (NDA) personnel

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 This guide contains good practices for the selection, training, qualification, and professional development of personnel performing analysis, calibration, physical measurements, or data review using nondestructive assay equipment, methods, results, or techniques. The guide also covers NDA personnel involved with NDA equipment setup, selection, diagnosis, troubleshooting, or repair. Selection, training, and qualification programs based on this guide are intended to provide assurance that NDA personnel are qualified to perform their jobs competently. This guide presents a series of options but does not recommend a specific course of action.

  12. 12 CFR 208.35 - Qualification requirements for transactions in certain securities. [Reserved

    Science.gov (United States)

    2010-01-01

    ... requirements for transactions in certain securities. [Reserved] ... 12 Banks and Banking 2 2010-01-01 2010-01-01 false Qualification requirements for transactions in certain securities. [Reserved] 208.35 Section 208.35 Banks and Banking FEDERAL RESERVE SYSTEM BOARD OF...

  13. Qualifications of persons working in radiation user's organization and radiation protection training required for competence

    International Nuclear Information System (INIS)

    2004-04-01

    The Guide sets out the requirements governing the qualifications of persons working in userAes organizations and the radiation protection training required for such competence. It also sets out the requirements for training organizations arranging radiation safety officer training and exams. The Guide applies only to uses of radiation requiring a afety licence. The requirements for userAes organizations are set out in Guide ST 1.4

  14. International Space Station (ISS) Internal Active Thermal Control System (IATCS) New Biocide Selection, Qualification and Implementation

    Science.gov (United States)

    Wilson, Mark E.; Cole, Harold E.; Rector, Tony; Steele, John; Varsik, Jerry

    2011-01-01

    The Internal Active Thermal Control System (IATCS) aboard the International Space Station (ISS) is primarily responsible for the removal of heat loads from payload and system racks. The IATCS is a water based system which works in conjunction with the EATCS (External ATCS), an ammonia based system, which are interfaced through a heat exchanger to facilitate heat transfer. On-orbit issues associated with the aqueous coolant chemistry began to occur with unexpected increases in CO2 levels in the cabin. This caused an increase in total inorganic carbon (TIC), a reduction in coolant pH, increased corrosion, and precipitation of nickel phosphate. These chemical changes were also accompanied by the growth of heterotrophic bacteria that increased risk to the system and could potentially impact crew health and safety. Studies were conducted to select a biocide to control microbial growth in the system based on requirements for disinfection at low chemical concentration (effectiveness), solubility and stability, material compatibility, low toxicity to humans, compatibility with vehicle environmental control and life support systems (ECLSS), ease of application, rapid on-orbit measurement, and removal capability. Based on these requirements, ortho-phthalaldehyde (OPA), an aromatic dialdehyde compound, was selected for qualification testing. This paper presents the OPA qualification test results, development of hardware and methodology to safely apply OPA to the system, development of a means to remove OPA, development of a rapid colorimetric test for measurement of OPA, and the OPA on-orbit performance for controlling the growth of microorganisms in the ISS IATCS since November 3, 2007.

  15. DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

    International Nuclear Information System (INIS)

    1999-04-01

    This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ''Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,'' and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently

  16. DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-04-01

    This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ``Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,`` and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently.

  17. Process qualification and control in electron beams--requirements, methods, new concepts and challenges

    International Nuclear Information System (INIS)

    Mittendorfer, J.; Gratzl, F.; Hanis, D.

    2004-01-01

    In this paper the status of process qualification and control in electron beam irradiation is analyzed in terms of requirements, concepts, methods and challenges for a state-of-the-art process control concept for medical device sterilization. Aspects from process qualification to routine process control are described together with the associated process variables. As a case study the 10 MeV beams at Mediscan GmbH are considered. Process control concepts like statistical process control (SPC) and a new concept to determine process capability is briefly discussed

  18. 76 FR 35103 - Training and Qualification Requirements for Check Airmen and Flight Instructors; Technical Amendment

    Science.gov (United States)

    2011-06-16

    ... which initial and transition flight training must include an in-flight element. Technical Amendment This.... 28471; Amendment Nos. 121-355 and 135-125] RIN 2120-AF08 Training and Qualification Requirements for Check Airmen and Flight Instructors; Technical Amendment AGENCY: Federal Aviation Administration (FAA...

  19. 12 CFR 14.60 - Qualification and licensing requirements for insurance sales personnel.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Qualification and licensing requirements for insurance sales personnel. 14.60 Section 14.60 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF... insurance product or annuity in any part of its office or on its behalf, unless the person is at all times...

  20. Requirements on qualification, competence and sufficient number of personnel for NPP operation

    International Nuclear Information System (INIS)

    Simon, M.

    2004-01-01

    The safe operation of NPPs presupposes qualified personnel on site in sufficient numbers. While the acquisition and preservation of technical expertise and the qualification of the shift personnel and other staff is well regulated by regulatory guidelines in Germany, there is a lack of such regulations with the exception for shift personnel - for the minimum number of technical personnel required for safe operation of a NPP. By order of the BMU, an attempt was made with this study to work out the requirements for qualification, competence and number of personnel to be maintained at the plant, representing the minimum requirements for safe operation of a NPP. The scope of the project was restricted to requirements for technical plant personnel. The aim was to work out requirements which would be as independent as possible of the existing organisation in a particular power plant. This study therefore does not assume a given organisational structure but was rather more oriented on the work processes in a NPP which are the basis for planning and performing routine work in the plant. For the study a work process model of typical tasks in a NPP had to be developed. Then, the tasks to be performed within the so defined work processes were described (task profiles) on the basis of existing manuals for plant organisation. From these task profiles such tasks were defined or selected which shall not be delegated to external personnel for specific reasons, and which were called vital competences. To keep these vital competences at the plant, an assessment and/or calculation of the necessary number of plant technical personnel was made using the task profiles for responsible personnel, but also by the evaluation of thousands of work orders for maintenance personnel. On the basis of these data, a proposal was made for the minimal number of technical personnel which is necessary to operate a NPP unit safely. Beside of this number, general criteria were developed which should be

  1. 14 CFR 253.8 - Qualifications to notice requirements.

    Science.gov (United States)

    2010-01-01

    ... to notice requirements. (a) If notice is not provided in accordance with § 253.5 at a ticket sales location outside of the United States that is not a U.S. air carrier ticket office, the price paid for the portion of such ticket that is for interstate and overseas air transportation shall be refundable without...

  2. Meeting the latest qualification requirements for Class 1E protection system equipment: a practical approach

    International Nuclear Information System (INIS)

    Daigle, R.P.; Breen, R.J.

    1977-01-01

    The requirements for qualifying Class 1E equipment for Nuclear Power Generating Stations were significantly revised in 1974 and 1975. These new requirements reflect the desire of the industry to provide improved methods of determining the qualification of this vital equipment. The revised standards do, in fact, meet these industry goals in a generally acceptable manner. The Nuclear Regulatory Commission is presently requiring utilities to comply with these revised standards and regulatory guides in order to obtain the necessary permits. Manufacturers are developing and implementing programs to comply with the new requirements. One of the more difficult new requirements of qualification is aging to achieve advanced life condition. The objectives and methods described for aging are difficult for much of the equipment within the Protection System. The use of thermal and vibrational techniques to simulate aging is valid for some components (i.e., capacitors, transistors, cable and/or motor insulation) but may be neither valid nor practical for many items (e.g., complete instrument systems, etc.). A seemingly obvious approach, although rarely followed, in regarding new or revised standards is to refrain from making any type of commitment until the standards are thoroughly understood. Often too hasty a decision is made by a utility (concerned about licensing) or a manufacturer (concerned about being competitive) to commit to new requirements. Consequently, the broad range of interpretations that usually develops for a given set of requirements may result in difficult relations between organizations. This paper deals with solutions for qualification in a practical sense, with emphasis on the aging issue and does not elaborate on seismic qualification

  3. Analyzing the Required Professional Qualification for Agricultural Extension Experts in Operational Level in the Mazandaran Province

    Directory of Open Access Journals (Sweden)

    Amir Ahmadpour

    2015-08-01

    Full Text Available Extension experts who play an active role at the operational level are required to have some indispensable competencies to enable them to provide the rural community with some high quality, ­applicable and important educational programs. Accordingly, the study sought to analyze the components of professional qualifications for agricultural extension experts’ operational level. This study is a descriptive and survey research. The statistical population (Agricultural Extension Experts in Operational Levels was comprised of 290 persons. And the proportional stratified sampling using Krejcie-Morgan Table was applied and 165 subjects were selected. The data collection tool was a researcher-made questionnaire, and its content validity was approved by agricultural extension experts and by using KMO coefficient and Bartlett’s Test giving a reliability of KMO=0.737(. The data analysis results showed that seven extracted factors of (research factors, technical-professional factors, teaching factors, managerial factors, personality factors, communication factors and virtual technology factors explain 63.691% of the total variance of the professional competencies for agriculture extension experts’ operational levels in the province. The  findings indicate that based on scientific methods of research,  assessment of needs, planning and assessment, and in-service training workshops implementation for experts seem to be necessary. Distinctive attention should be practiced by Agriculture Organization to improve agents’ skills in a variety of crops cultivation and in working with software and agricultural applications.

  4. Challenges faced in selection, manufacture, quality assurance and qualification of the components for FBTR CRDM applications

    International Nuclear Information System (INIS)

    Ramesh, E.; Krovvidi, S.C.S.P. Kumar; Sarangarajan, S.; Kasinathan, N.; Srinivasan, G.

    2015-01-01

    Fast Breeder Test Reactor (FBTR) is a sodium cooled type experimental reactor. Six numbers of Control Rod Drive Mechanisms (CRDM) along with their B4C control rods perform reactor start up, controlled shutdown, reactivity control for power changing and burn-up compensation and to shut down the reactor by SCRAM action during abnormal conditions. Lower part of the CRDM which consists of translation tube, outer sheath and gripper is partially immersed in sodium. Nested Ripple type Welded Disc Bellows (NRWDB) called translation bellows prevents entry of sodium in the space between the translation tube and outer sheath and acts as primary leak tight barrier. Silicone bellows which is near ground level elevation acts as secondary leak tight barrier. Non standard Aluminium bronze rod was used as raw material for various drive components in CRDM. These components were imported earlier from FRANCE. Indigenous development of these items and bellows was taken up due to difficulties in procurement. Extensive studies were carried out on selection of materials, establishment of manufacturing procedures and stringent Quality Assurance Program (QAP) to ensure defect free component during indigenous development. Suitable methodology was arrived for qualification of these components. Successful development of silicone bellows and Aluminium bronze rods were completed as per our requirements and selection, establishment of manufacturing procedure and QAP were completed for (NRWDB). Prototype development of NRWDB is in progress. (author)

  5. A new approach to determine the environmental qualification requirements for the safety related equipment

    International Nuclear Information System (INIS)

    Hasnaoui, C.; Parent, G.

    2000-01-01

    The objective of the environmental qualification of safety related equipment is to ensure that the plant defense-in-depth is not compromised by common mode failures following design basis accidents with a harsh environment. A new approach based on safety functions has been developed to determine what safety-related equipment is required to function during and after a design basis accident, as well as their environmental qualification requirements. The main feature of this approach is to use auxiliary safety functions established from safety requirements as credited in the safety analyses. This approach is undertaken in three steps: identification of the auxiliary safety functions of each main safety function; determination of the main equipment groups required for each auxiliary safety function; and review of the safety analyses for design basis accidents in order to determine the credited auxiliary safety functions and their mission times for each accident scenario. Some of the benefits of the proposed approach for the determination of the safety environmental qualification requirements are: a systematic approach for the review of safety analyses based on a safety function check list, and the insurance, with the availability of the safety functions, that Gentilly-2 defense-in-depth would not be compromised by design basis accidents with a harsh environment. (author)

  6. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  7. Technical qualification requirements and training programs for radiation protection personnel at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Copenhaver, E.D.; Houser, B.S.; Butler, H.M. Jr.; Bogard, J.S.; Fair, M.F.; Haynes, C.E.; Parzyck, D.C.

    1986-04-01

    This document deals with the policies and practices of the Environmental and Occupational Safety Division (EOSD) at the Oak Ridge National Laboratory (ORNL) in regard to the selection, training, qualification, and requalification of radiation protection staff assigned to reactor and nonreactor nuclear facilities. Included are personnel at facilities that: (1) operate reactors or particle accelerators; (2) produce, process, or store radioactive liquid or solid waste; (3) conduct separations operations; (4) engage in research with radioactive materials and radiation sources; and (5) conduct irradiated materials inspection, fuel fabrication, deconamination, or recovery operations. The EOSD personnel also have environmental surveillance and operational and industrial safety responsibilities related to the total Laboratory

  8. Licensing requirements regarding the qualification of operating personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Fechner, J.B.

    1981-01-01

    The legal requirements regarding the qualifications of operating personnel in nuclear power plants in the Federal Republic of Germany are outlined as in article 7 of the Atomic Energy Act. For the responsible operating personnel the requisite competence and reliability are legally required; for subordinate personnel the law requires only the necessary knowledge. The requisite competence and the necessary knowledge have been further specified in a set of guidelines by the authorities; work on specification of reliability requirements is under way. Essential elements of the requisite competence of responsible operating personnel are their professional qualification, their safety-related knowledge, their abilities, their practical experience, and - for the responsible shift personnel - their nuclear, plant-related training as well as a written and oral examination. Requalification is indispensible for keeping the requisite competence on a level in accordance with the current state of science and technology. Facts concerning the personal reliability of the responsible operating personnel are assessed by the competent authorities on the basis of information available at other state institutions. For the responsible shift personnel, physical and psychological fitness are important factors contributing to their reliability. The necessary knowledge subordinate operating personnel must possess with respect to plant safety and safety of the personnel is assured via instruction on safety and via special briefings at the working place. Lack of safety-related knowledge has to be compensated for by assigning an experienced permanent supervisor for each activity in question. Current work on qualification of operating personnel concentrates on training, including simulator training, of responsible shift personnel. (author)

  9. Component-Level Selection and Qualification for the Global Ecosystem Dynamics Investigation (GEDI) Laser Altimeter Transmitter

    Science.gov (United States)

    Frese, Erich A.; Chiragh, Furqan L.; Switzer, Robert; Vasilyev, Aleksey A.; Thomes, Joe; Coyle, D. Barry; Stysley, Paul R.

    2018-01-01

    Flight quality solid-state lasers require a unique and extensive set of testing and qualification processes, both at the system and component levels to insure the laser's promised performance. As important as the overall laser transmitter design is, the quality and performance of individual subassemblies, optics, and electro-optics dictate the final laser unit's quality. The Global Ecosystem Dynamics Investigation (GEDI) laser transmitters employ all the usual components typical for a diode-pumped, solid-state laser, yet must each go through their own individual process of specification, modeling, performance demonstration, inspection, and destructive testing. These qualification processes and results for the laser crystals, laser diode arrays, electro-optics, and optics, will be reviewed as well as the relevant critical issues encountered, prior to their installation in the GEDI flight laser units.

  10. Qualification of Simulation Software for Safety Assessment of Sodium Cooled Fast Reactors. Requirements and Recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pointer, William David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sieger, Matt [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Moe, Wayne [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); HolbrookINL, Mark [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    The goal of this review is to enable application of codes or software packages for safety assessment of advanced sodium-cooled fast reactor (SFR) designs. To address near-term programmatic needs, the authors have focused on two objectives. First, the authors have focused on identification of requirements for software QA that must be satisfied to enable the application of software to future safety analyses. Second, the authors have collected best practices applied by other code development teams to minimize cost and time of initial code qualification activities and to recommend a path to the stated goal.

  11. An overview of fiber-to-the-premises (FTTP) product requirements and qualification programs

    Science.gov (United States)

    Gebizlioglu, Osman S.; Gallo, Ernest J.

    2006-04-01

    North American deployments of FTTP architectures have been rapidly increasing. While the FTTP market is being driven by major telecommunications service providers, equipment suppliers have been scrambling to bring products to market that will ensure them a piece of this high-stakes market. In this invited presentation/paper, we propose to examine the technical requirements that are needed to support the new FTTP network with a host of new products that have been in development. To enable service providers select the best new products for FTTP deployment, product selection needs to be based on the analysis and testing of new products for performance and reliability, Telcordia, in its traditional role of telecommunications standards development, has been publishing generic requirements (GR) documents that have been used by suppliers, service providers and the industry at large. Product qualification programs based on the established performance and reliability requirements/standards have been designed to evaluate products to determine if they can 1) withstand the rigors of the outside plant deployment environment and perform for extended periods of time, 2) be upgradeable, and 3) craft friendly. The outside plant is a tough environment to live in. A product must perform under the extreme conditions of cold down -40°C (-40°F) and hot up to 46°C (115°F) with high humidity of 95%, rain, snow, sleet, vibration due to traffic, lightning, heating due to solar loads, high winds, ice, sand storms, and products are even tested to demonstrate if they can continue to operate in an earthquake, a wild fire and a shotgun blast. All FTTP products are not only expected to perform, but they must meet stringent optical performance criteria of low insertion loss and reflectance / return loss at a broad range of wavelengths from 1310, 1490, 1550 and 1625 nm. While the upstream (from the customer to the CO) voice and data transmission is currently planned over 1310-nm wavelength, the

  12. Guidelines for Selection, Screening and Qualification of Low-Voltage Commercial Multilayer Ceramic Capacitors for Space Programs

    Science.gov (United States)

    Teverovsky, Alexander A.

    2012-01-01

    This document has been developed in the course of NASA Electronic Parts and Packaging (NEPP) program and is not an official endorsement of the insertion of commercial capacitors in space programs or an established set of requirements for their testing. The purpose of this document is to suggest possible ways for selection, screening, and qualification of commercial capacitors for NASA projects and open discussions in the parts engineering community related to the use of COTS ceramic capacitors. This guideline is applicable to commercial surface mount chip, simple parallel plate design, multi-layer ceramic capacitors (MLCCs) rated to voltages of 100V and less. Parts with different design, e.g. low inductance ceramic capacitors (LICA), land grid array (LGA) etc., might need additional testing and tailoring of the requirements described in this document. Although the focus of this document is on commercial MLCCs, many procedures discussed below would be beneficial for military-grade capacitors

  13. Environmental qualification design for NPP refurbishment to comply with revised licensing requirements

    International Nuclear Information System (INIS)

    MacBeth, M. J.; Hemmings, R. L.

    2002-01-01

    Recent Canadian Nuclear Regulatory decisions have imposed Environmental Qualification (EQ) requirements for twenty-four Reactor Building (RB) airlocks at the four-unit Pickering Nuclear Generating Station-B (PNGS-B) facility. This paper describes the EQ modification design work completed by CANATOM-NPM for the problematic aspects for such projects. The airlocks allow RB access while providing a containment boundary and are designed to prevent a potential breach of containment for all analysed station conditions. Each PNGS-B unit has three large equipment airlocks and three smaller personnel airlocks. The airlocks must function under postulated worst-case design basis accident(DBA) conditions for assigned mission durations. The design must ensure that accident conditions cannot spuriously initiate an un-requested door opening. CANATOM-NPM reviewed site data to specify the necessary EQ modifications required to satisfy licensing requirements while providing a correct and complete as-found record of the existing airlock installation. The design team assessed the installed airlocks configuration against environmental qualification requirements to finalize the list of necessary modifications. A comprehensive, cross-discipline review of proposed design changes was completed to identify any further changes required to satisfy the final EQ licensing goal. The design team also conducted a design review of the EQ modification installation strategy to integrate the design deliverables with the installation team requirements while attempting to minimize necessary outage time for EQ modification installations. This project was completed on schedule and within the cost limitations required by the client with comprehensive, high quality final design packages. Overall improvements were realized for OPG system drawings and the electronic documentation of design data. The EQ modifications designed by CANATOM-NPM will ensure the continued operation of the PNGS-B NPP past December 31

  14. Seismic qualification of equipment

    International Nuclear Information System (INIS)

    Heidebrecht, A.C.; Tso, W.K.

    1983-03-01

    This report describes the results of an investigation into the seismic qualification of equipment located in CANDU nuclear power plants. It is particularly concerned with the evaluation of current seismic qualification requirements, the development of a suitable methodology for the seismic qualification of safety systems, and the evaluation of seismic qualification analysis and testing procedures

  15. Current challenges for radiographers and following changes in the education and the qualification requirements

    International Nuclear Information System (INIS)

    Taneva, E.; Gagova, E.

    2006-01-01

    Full text: The communication is intended to present the new requisites for the activity of the X-ray laboratory assistant, laying changes in the educational background and the qualification of the respective medical specialists. The need of new knowledge and skills lead to changes in the competence of the X-ray laboratory assistants and call for urgent measures for updating the curriculum, programmes and exercises. The implementation of new technologies in the profession requires an education of new quality that complies with the needs of the health care in the country and harmonizing it with the requirements of the European Union. Having made an analysis of the education so far and comparing its condition with that of the leading European countries we came to the conclusion that not only the contents of the education should be changed, but also the teaching hours and the qualification of the X-ray laboratory assistants. Knowing the new realities and challenges in the health care system, the professors of the medical colleges and the health specialists are aware of the need to introduce changes in the medical practice and work together for its implementation

  16. IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

  17. The Impact of Automation on Job Requirements and Qualifications for Catalogers and Reference Librarians in Academic Libraries.

    Science.gov (United States)

    Xu, Hong

    1996-01-01

    Compares and analyzes job advertisements for catalogers and reference librarians in academic libraries from 1971 to 1990 to trace the impact of automation on job requirements and qualifications. Findings indicate that computer skills are needed, and there are more entry-level jobs being posted for both groups. (Author/JMV)

  18. 1E Qualification of Electrical Equipment - Requirement for Safety Nuclear Power Plants

    International Nuclear Information System (INIS)

    Geambasu, C.; Segarceanu, D.; Albu, J.

    2002-01-01

    The paper presents the qualification methods of the safety related equipment according to the safety class 1E. There are presented the qualification principles, procedure and documents, emphasis being laid on the qualification approach by type tests. This approach assumes the equipment test under both normal and accident conditions (design basis events) simulating the operational conditions and covers the largest part of electrical equipment from a nuclear power plant.The safety related equipment is to be qualified is subjected to a sequential test that will be detailed in the paper. (author)

  19. 40 CFR 60.2635 - What are the operator training and qualification requirements?

    Science.gov (United States)

    2010-07-01

    ...) Combustion controls and monitoring. (v) Operation of air pollution control equipment and factors affecting... Construction On or Before November 30, 1999 Model Rule-Operator Training and Qualification § 60.2635 What are...

  20. 40 CFR 62.14595 - What are the operator training and qualification requirements?

    Science.gov (United States)

    2010-07-01

    ... control equipment and factors affecting performance (where applicable). (vi) Inspection and maintenance of... Commenced Construction On or Before November 30, 1999 Operator Training and Qualification § 62.14595 What...

  1. Design of fuelling machine bridge and carriage to meet seismic qualification requirements

    International Nuclear Information System (INIS)

    Ghare, A.B.; Chhatre, A.G.; Vyas, A.K.; Bhambra, H.S.

    1996-01-01

    During each refuelling operation, the boundary of Primary heat transport system is extended up to Fuelling Machines. A breach in the pressure boundary of Fuelling Machine in this condition would cause a loss of coolant accident. Fuelling Machines are also used for transit storage of spent fuel bundles till discharged to fuel transfer system. Therefore, a fuelling machine, including its support structures, is required to be seismically qualified for both on-reactor ( coupled ) mode and off-reactor (uncoupled) mode. The fuelling machine carriage used in the first generation of Indian PHWRs is a mobile equipment on wheels moving over fixed rails. As this configuration was found unsuitable for withstanding strong seismic disturbances, a bridge type design with fixed columns was evolved for the next generation of reactors. Initially, the seismic analysis of the fuelling machine bridge and carriage was done using static structural analysis and values of natural frequencies for various structures were computed. The structures were suitably modified based on the results of this analysis. Subsequently, a detailed dynamic seismic analysis using finite element model has been completed for both coupled and uncoupled conditions. The qualification of the structure has been carried out as per ASME section 111 Division 1, sub section NF. Details of the significant design features, static and dynamic analysis, results and conclusions are given in the presentation. (author). 4 refs., 4 tabs., 7 figs

  2. Design of fuelling machine bridge and carriage to meet seismic qualification requirements

    Energy Technology Data Exchange (ETDEWEB)

    Ghare, A B; Chhatre, A G; Vyas, A K; Bhambra, H S [Nuclear Power Corporation of India Ltd., Mumbai (India)

    1997-12-31

    During each refuelling operation, the boundary of Primary heat transport system is extended up to Fuelling Machines. A breach in the pressure boundary of Fuelling Machine in this condition would cause a loss of coolant accident. Fuelling Machines are also used for transit storage of spent fuel bundles till discharged to fuel transfer system. Therefore, a fuelling machine, including its support structures, is required to be seismically qualified for both on-reactor ( coupled ) mode and off-reactor (uncoupled) mode. The fuelling machine carriage used in the first generation of Indian PHWRs is a mobile equipment on wheels moving over fixed rails. As this configuration was found unsuitable for withstanding strong seismic disturbances, a bridge type design with fixed columns was evolved for the next generation of reactors. Initially, the seismic analysis of the fuelling machine bridge and carriage was done using static structural analysis and values of natural frequencies for various structures were computed. The structures were suitably modified based on the results of this analysis. Subsequently, a detailed dynamic seismic analysis using finite element model has been completed for both coupled and uncoupled conditions. The qualification of the structure has been carried out as per ASME section 111 Division 1, sub section NF. Details of the significant design features, static and dynamic analysis, results and conclusions are given in the presentation. (author). 4 refs., 4 tabs., 7 figs.

  3. Water requirements of selected industries

    Science.gov (United States)

    ,; Mussey, Orville D.; Conklin, Howard L.; Durfor, Charles N.; Otts, Louis Ethelbert; Walling, Faulkner B.

    1955-01-01

    The early industries in America generally were established when and where demands for the products of industry arose. Most of the early industries were so located that their increasing requirements for transportation, raw materials, market, labor, and water supply could be satisfied economically. Many of these original plant locations have continued as modern industrial centers and their output has increased manyfold in meeting the demands of our growing Nation. The recent and current industrial expansion and the trend toward the growth of chemical industries, many Of which are heavy users of water, has resulted in a tremendous increase in the total withdrawal of water for industrial use as well as a large increase in the per capita use of water. This increase in industrial water requirement has strained the capacity of the developed water supplies in many areas, and in some instances the adequacy of the potential water supplies is questionable. The Geological Survey is engaged in preparing and publishing a series of reports describing the developed and undeveloped water resources of many important industrial areas. This work was started initially at the request of the National Securities Resources Board as a means to insure that water supplies are adequate for our rapidly expanding industrial development. Although many factors contribute to establishing the feasibility or even the limits of future industrial development, the one relating to available water supply is extremely important. A knowledge of the water requirements of various industries is valuable therefore in planning the logical development in any area where water supply is a critical factor. Thus far very little suitable information on the water requirements of our major industries is available for general planning. An inventory of unit water-use values in industry therefore would be generally helpful and also might tend to stimulate water-conservation methods. To obtain such information

  4. Development of the environmental qualification safety requirement matrix for the containment system of in-service CANDU reactors

    International Nuclear Information System (INIS)

    Chun, R.M.; Low, J.; Sobolewski, J.

    1994-01-01

    Over the last several years, Ontario Hydro Nuclear (OHN) has placed increasing emphasis on environmental qualification (EQ) at its Pickering and Bruce NGS A and B nuclear generating stations (NGSs). The program currently underway (at the time of the conference) builds upon the experience gained from the extensive Darlington NGS EQ experience and from EQ programs conducted by other utilities. Some of the major steps of the OHN EQ program include: defining Safety Requirement Matrices (SRMs), establishing environmental conditions, developing an EQ List, conducting an EQ Assessment and maintaining Operational EQ Assurance during the plant life. The SRM identifies safety related components, their required safety functions and their mission times for each postulated design basis accident (DBA). This is a critical step, as the SRM defines the equipment that requires assurance of EQ and precise requirements must be provided to ensure a cost effective EQ program. This paper describes the development of the SRMs for the containment system of the Bruce stations. The introductory section briefly discusses how the industry has dealt with equipment qualification as it has evolved and the role of the SRMs in the OHN EQ Program. In Section 2, the preparation of the SRM is described along with the applicable ground rules used. The results of the application of the SRM preparation guidelines to the containment system are discussed in Section 3. A summary of the major findings and conclusions is presented. 3 refs., 3 figs

  5. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

  6. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training

  7. What are the qualifications and selection criteria for women to be appointed to society journal editorial boards?

    Science.gov (United States)

    Tomizawa, Yasuko

    2014-02-01

    Japan ranks extremely low in global ranking of gender equality. It is not easy for female doctors to acquire leadership positions in member societies of the Japanese Association of Medical Science (JAMS). Very few women are included on editorial boards of English medical journals in Japan. Furthermore, until last year, there had been no female editors in English language journals of surgical societies. The qualifications and criteria for selecting editorial board members of medical journals should be clarified. Medical journals in Japan would gain diversity by including women on editorial boards in the same proportion as women membership in the corresponding medical societies.

  8. Benefits of Digital Equipment Generic Qualification Activities

    International Nuclear Information System (INIS)

    Thomas, James E.; Steiman, Samuel C.

    2002-01-01

    As a result of nuclear power plant instrumentation and control obsolescence issues, there have been numerous activities during recent years relating to the qualification of digital equipment. Some of these activities have been 'generic' in nature in that the qualification was not limited to plant specific applications, but was intended to cover a broad base of potential applications of the digital equipment. These generic qualifications have been funded by equipment manufacturers and by utility groups and organizations. The generic activities sponsored by the Electric Power Research Institute (EPRI) have been pilot projects for an overall generic qualification approach. The primary benefit resulting from the generic qualification work to date is that a number of digital platforms and digital devices are now available for use in various nuclear safety-related applications. Many of the tests and evaluations necessary to support plant specific applications have been completed. The amount of data and documentation that each utility must develop on a case by case basis has been significantly reduced. There are also a number of additional benefits resulting from these industry efforts. The challenges and difficulties in qualifying digital equipment for safety-related applications are now more clearly understood. EPRI has published a lessons learned document (EPRI Report 1001452, Generic Qualification of Commercial Grade Digital Devices: Lessons Learned from Initial Pilots, which covers several different qualification areas, including device selection, project planning, vendor surveys and design reviews, and electromagnetic compatibility (EMC) qualification. Application of the experience and lessons learned from the EPRI pilot activities should help reduce the effort and cost required for future qualification work. Most generic qualification activities for commercial equipment have been conducted using the approach of EPRI TR-106439, Guideline on Evaluation and Acceptance

  9. Work required for selective quantum measurement

    Science.gov (United States)

    Konishi, Eiji

    2018-06-01

    In quantum mechanics, we define the measuring system M in a selective measurement by two conditions. Firstly, when we define the measured system S as the system in which the non-selective measurement part acts, M is independent from the measured system S as a quantum system in the sense that any time-dependent process in the total system S  +  M is divisible into parts for S and M. Secondly, when we can separate S and M from each other without changing the unitary equivalence class of the state of S from that obtained by the partial trace of M, the eigenstate selection in the selective measurement cannot be realized. In order for such a system M to exist, we show that in one selective measurement of an observable of a quantum system S 0 of particles in S, there exists a negative entropy transfer from M to S that can be directly transformed into an amount of Helmholtz free energy of where T is the thermodynamic temperature of the system S. Equivalently, an extra amount of work, , is required to be done by the system M.

  10. 1994 report on Tasks 4.3.1 and 4.3.2: Survey of anticipated requirements and qualification requirements for OSS

    International Nuclear Information System (INIS)

    Silvani, V.

    1995-01-01

    This is a preliminary report summarizing some topics related to the survey on functional and qualification requirements of Operator Support Systems (OSS's) in NPP's. This document has been prepared on the basis of the information presented in the previous meetings of this CRP working group. Additional information are expected when the answers to the working group questionnaire will be available. Functionalities examined are those referring to system functions and user's needs; technology trends are also considered. For practical purposes this document is divided in the followings: Summary of major OSS requirements and related problems as derived from the existing literature; appendix 1 reporting a summary of major functions performed by the OSS's presently in operation or under development in laboratories; appendix 2 reporting the list of standards for critical software. 18 refs, tabs

  11. Materials selection, qualification and manufacturing of the in-vessel divertor cryopump for JET

    International Nuclear Information System (INIS)

    Papastergiou, S.; Obert, W.; Thompson, E.

    1994-01-01

    The introduction of a cryopump into the interior of a large tokamak raises several technical problems related to the thermal stresses, eddy current forces and choice of materials. The JET divertor cryopump has been optimized in terms of stresses, flow stability and operation - the liquid nitrogen cooled chevron structure in particular having to fulfill conflicting requirements at cryogenic temperatures. These requirements include good thermal conductivity in order to minimize thermal gradients (to reduce the radiative heat load onto the liquid helium circuit), high electrical resistivity (to minimize eddy current stresses), high mechanical strength and good mechanical formability. This paper reports on the materials selection based on measurements of properties at cryogenic and elevated temperatures and the development of an optimized thermal treatment combining solution heat treatment, brazing and precipitation hardening. It also reports on the successful development of various manufacturing technologies which have been employed including (a) techniques for brazing of the chosen copper alloy onto inconel and stainless steel, (b) surface blackening of the copper alloy with plasma sprayed ceramic coatings that are vacuum compatible and able to withstand temperatures between 70 K and 1135 K and (c) plasma spray deposition of copper onto stainless steel in order to produce an anisotropic composite material with improved thermal conductivity, high strength and high electrical resistivity for use at temperatures between 70 K and 650 K

  12. Reaction Qualifications Revisited

    DEFF Research Database (Denmark)

    Lippert-Rasmussen, Kasper

    2009-01-01

      When, in a competitive sphere, people are selected on the basis of qualifications only, their chances of acquiring positions of advantage may seem to depend entirely upon their abilities, not discriminatory bias. However, if reaction qualifications - i.e. characteristics which contribute...... to a person's effectiveness by causing a favourable reaction in customers, co-workers etc. (for short: recipients) - are involved, this assumption is false. Building on work by Wertheimer, Mason, and Miller, this paper proposes an account of the reaction qualifications that count, from the point of view...... of merit. Specifically, it preserves symmetry between negative evaluations of antimeritocratic bases of selection and negative evaluations of qualifications rooted in comparable antimeritocratic reactions. So if employers should not select among applicants on the basis of their (the employers') racial...

  13. Survey of foreign reactor operator qualifications, training, and staffing requirements. Final report

    International Nuclear Information System (INIS)

    Au, M.L.; DiSalvo, R.; Merschoff, E.

    1982-05-01

    The report is a compilation of the data obtained from a survey of foreign nuclear power plant operator requirements. Included among the considerations are: (1) shift staffing; (2) operator eligibility; (3) operator training programs; (4) operator licensing or certification; and (5) operator retraining. The data obtained from this survey are presented in matrix form and contrasted with U.S. requirements

  14. 78 FR 42323 - Pilot Certification and Qualification Requirements for Air Carrier Operations

    Science.gov (United States)

    2013-07-15

    ... leadership, professionalism, and mentoring skills, stabilized approaches, and operations in icing conditions... leadership, professionalism, and first officer assertiveness (Recommendation A-10- 15 and A-11-39); Require... fundamentals of instruction. [[Page 42331

  15. 77 FR 37287 - Implementation of Statutory Amendments Requiring the Qualification of Manufacturers and Importers...

    Science.gov (United States)

    2012-06-21

    ... Permit Requirements, and the Expanded Definition of Roll-Your-Own Tobacco AGENCY: Alcohol and Tobacco Tax and Trade Bureau, Treasury. ACTION: Final rule; Treasury decision. SUMMARY: The Alcohol and Tobacco Tax and Trade Bureau is making permanent, with some changes, temporary regulatory amendments...

  16. Selection processes in a Delphi study about key qualifications in Senior Secondary Vocational Education

    NARCIS (Netherlands)

    Zolingen, S.J. van; Klaassen, C.A.C.

    2003-01-01

    The focus of this study is the Delphi method. First, a short history of the Delphi method is given. Then, different types of the Delphi method are described, and the validity and reliability of the Delphi method are discussed. Finally, this study reports on the selection processes and assessments

  17. Requirements Specification for Open Source Software Selection

    OpenAIRE

    YANG, YING

    2008-01-01

    Open source software has been widely used. The software world is enjoying the advantages of collaboration and cooperation in software development and use with the advent of open source movement. However, little research is concerned about the practical guidelines of OSS selection. It is hard for an organization to make a decision whether they should use the OSS or not, and to select an appropriate one from a number of OSS candidates. This thesis studies how to select an open source software f...

  18. Checking the special professional qualification of selected personnel of Czechoslovak nuclear power facilities

    International Nuclear Information System (INIS)

    Kovar, P.; Bahnova, V.

    1990-01-01

    The system of examinations of selected staff members of Czechoslovak nuclear power plants for their special professional quanlification is described in detail. This selected personnel includes secondary circuit operators, primary circuit operators, graduate shift leaders as well as reactor unit managers. Attention is paid to the structure, methodology, contents and criteria of evaluation of the written, oral and practical parts of the examination, which is sat for before the State Examination Commission. Based on the results of the examinations, the Czechoslovak Atomic Energy Commission grants, prolongs or cancels licenses for the particular functions. Over the period from 1985 to March 1989, 394 new licenses were issued, 93 licenses were prolonged and 4 were withdrawn. (Z.M.). 7 figs., 3 tabs., 3 refs

  19. Selection, training, qualification and licensing of Three Mile Island reactor operating personnel

    International Nuclear Information System (INIS)

    Eytchison, R.M.

    1980-01-01

    The various programs which were intended to staff Three Mile Island with competent, trained operators and supervisors are reviewed. The analysis includes a review of the regulations concerning operator training and licensing, and describes how the requirements were implemented by the NRC, Metropolitan Edison Company, and Babcock and Wilcox Company. Finally the programs conducted by these three organisations are evaluated. (U.K.)

  20. 40 CFR 205.57 - Selective enforcement auditing requirements.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Selective enforcement auditing requirements. 205.57 Section 205.57 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) NOISE... Selective enforcement auditing requirements. ...

  1. 40 CFR 205.160 - Selective enforcement auditing (SEA) requirements.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Selective enforcement auditing (SEA) requirements. 205.160 Section 205.160 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... Selective enforcement auditing (SEA) requirements. ...

  2. Energy Monitoring and Control Systems Operator Training - Recommended Qualifications, Staffing, Job Description, and Training Requirements for EMCS Operators.

    Science.gov (United States)

    1982-06-01

    start/stop chiller optimization , and demand limiting were added. The system monitors a 7,000 ton chiller plant and controls 74 air handlers. The EMCS does...Modify analog limits. g. Adjust setpoints of selected controllers. h. Select manual or automatic control modes. i. Enable and disable individual points...or event schedules and controller setpoints ; make nonscheduled starts and stops of equipment or disable field panels when required for routine

  3. Hybrid Qualifications

    DEFF Research Database (Denmark)

    Against the background of increasing qualification needs there is a growing awareness of the challenge to widen participation in processes of skill formation and competence development. At the same time, the issue of permeability between vocational education and training (VET) and general education...... has turned out as a major focus of European education and training policies and certainly is a crucial principle underlying the European Qualifications Framework (EQF). In this context, «hybrid qualifications» (HQ) may be seen as an interesting approach to tackle these challenges as they serve «two...

  4. On safety 1E qualification of electrical equipment for nuclear power stations

    International Nuclear Information System (INIS)

    Segarceanu, D.; Geambasu, C.; Avramescu, M.

    1995-01-01

    Electrical equipment and systems for the emergency shutdown of a nuclear reactor are qualified according to safety class 1E. Methods of qualification meeting the requirements should be used, either individually or in combination include, type-test qualification, qualification by operating experience, qualification by analysis, combined qualification. These methods qualification principles, procedures and documents are discussed. (N.T.). 1 fig

  5. 5 CFR 302.403 - Qualifications for promotion.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Qualifications for promotion. 302.403... EMPLOYMENT IN THE EXCEPTED SERVICE Selection and Appointment; Reappointment; and Qualifications for Promotion § 302.403 Qualifications for promotion. In determining qualifications for promotion with respect to an...

  6. 40 CFR 205.171 - Selective enforcement auditing (SEA) requirements.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Selective enforcement auditing (SEA) requirements. 205.171 Section 205.171 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... § 205.171 Selective enforcement auditing (SEA) requirements. ...

  7. Novel qualification methodology for subsea processing

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, Paal Jahre; Bratfos, Hans A. [Det Norske Veritas, Oslo (Norway)

    2004-07-01

    The purpose of the Reliability Analysis is to quantify the overall reliability of the technology to confirm that the functional requirements and the target reliability laid down in the Qualification Basis are met. On this basis DNV may issue a Statement of Fitness for Service affirming that the technology is considered qualified. Although a technology may be convincingly proven fit for service without using reliability measures, a quantified reliability makes the technology more competitive in a business where profitability is directly related to the reliability of the technology. In this respect it should also be noted that a reliability analysis require specific input data that sometimes must be derived by testing. It is therefore important to take this into consideration already in the selection and planning of qualification methods. (author)

  8. Qualification, training, licensing/authorization and retraining of operating personnel in nuclear power plants. Some requirements and practices commonly shared in the European Community Member States

    International Nuclear Information System (INIS)

    Pele, J.P.

    1987-01-01

    At the end of the fifties a treaty was signed instituting between six countries of the European Community for Atomic Energy, or in brief, Euratom. This treaty, in addition to the Common Market Treaty and the Coal and Steel one, constitutes the legal frame of the European Community which, at present, comprises 12 Member States. A commission, the so-called Commission of the European Communities (or in brief CEC) has to implement the provisions laid down in the treaties. Qualification, training, licensing and re-training of operating personnel have been the subjects of an in-depth exchange of views and information in the frame of the work conducted by the Commission. The evaluation of the regulations and practices in countries of the EC and some other countries having a large nuclear energy program, has led to the identification of some generally valid concepts. This synthesis, made with the assistance of a consultant, is now published under the form of an EUR report (EUR 10981). The main topics addressed within this report are the following: shift staffing and staffing of the control room, personnel selection, qualifications necessary for recruitment, training and retraining, and licensing/authorization

  9. Standard guide for qualification of measurement methods by a laboratory within the nuclear industry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide provides guidance for selecting, validating, and qualifying measurement methods when qualification is required for a specific program. The recommended practices presented in this guide provide a major part of a quality assurance program for the laboratory data (see Fig. 1). Qualification helps to assure that the data produced will meet established requirements. 1.2 The activities intended to assure the quality of analytical laboratory measurement data are diagrammed in Fig. 1. Discussion and guidance related to some of these activities appear in the following sections: Section Selection of Measurement Methods 5 Validation of Measurement Methods 6 Qualification of Measurement Methods 7 Control 8 Personnel Qualification 9 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitati...

  10. Qualification Test for Korean Mockups of ITER Blanket First Wall

    International Nuclear Information System (INIS)

    Kim, S. K.; Lee, D. W.; Bae, Y. D.; Hong, B. G.; Jung, H. K.; Jung, Y. I.; Park, J. Y.; Jeong, Y. H.; Choi, B. K.; Kim, B. Y.

    2009-01-01

    ITER First Wall (FW) includes the beryllium armor tiles joined to CuCrZr heat sink with stainless steel cooling tubes. This first wall panels are one of the critical components in the ITER machine with the surface heat flux of 0.5 MW/m 2 or above. So qualification program needs to be performed with the goal to qualify the joining technologies required for the ITER First Wall. Based on the results of tests, the acceptance of the developed joining technologies will be established. The results of this qualification test will affect the final selection of the manufacturers for the ITER First Wall

  11. Environmental qualification program for new designs

    International Nuclear Information System (INIS)

    Doerffer, K.

    2007-01-01

    Qualification of nuclear power plant equipment and components important to safety (ITS) is an integral part of the design process. The qualification methodology differs based on the severity of service conditions (operational and ambient), to which the ITS equipment is exposed. In Canada, the licensing requirements for environmental qualification for new designs are governed by the Canadian Standard Association (CSA) standard, N290.13-2005 titled 'Environmental Qualification of Equipment for CANDU Nuclear Power Plants' and the pre-consultation draft, 'Requirements for Design of Nuclear Power Plants'(DRD), issued for trial use by the Canadian Nuclear Safety Commission (CNSC) in March 2005. This paper will describe AECL's current Environmental Qualification program developed to comply with the above licensing requirements as applied to new designs. The focus will be given to qualification of ITS systems structures and components (SSC) to harsh conditions occurring due to the Design Basis Accidents (DBA). (author)

  12. Interim staff position on environmental qualification of safety-related electrical equipment: including staff responses to public comments. Regulatory report

    International Nuclear Information System (INIS)

    Szukiewicz, A.J.

    1981-07-01

    This document provides the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment, in the resolution of Unresolved Safety Issue A-24, 'Qualification of Class IE Safety-Related Equipment.' The positions herein are applicable to plants that are or will be in the construction permit (CP) or operating license (OL) review process and that are required to satisfy the requirements set forth in either the 1971 or the 1974 version of IEEE-323 standard

  13. Relationship between Air Traffic Selection and Training (AT-SAT)) Battery Test Scores and Composite Scores in the Initial en Route Air Traffic Control Qualification Training Course at the Federal Aviation Administration (FAA) Academy

    Science.gov (United States)

    Kelley, Ronald Scott

    2012-01-01

    Scope and Method of Study: This study focused on the development and use of the AT-SAT test battery and the Initial En Route Qualification training course for the selection, training, and evaluation of air traffic controller candidates. The Pearson product moment correlation coefficient was used to measure the linear relationship between the…

  14. Nuclear energy electricity technical regulation on the qualification

    International Nuclear Information System (INIS)

    1995-01-01

    It tells the range of application purpose and of the qualification. It describes how to qualify of the class 1 E equipment, which are type test, operating experience, analysis and combined method. Next it deals with qualification procedure, which are specification requirement, requirement of qualification program, type testing, operating experience, analysis and combined qualification, acceptance criteria modification and extension with qualified life, simulated test profiles and document about type test data, operating experience data and extrapolation.

  15. Professional Exam as a Tool for Forming the Trajectory of Improving the Qualification of an Employee

    Directory of Open Access Journals (Sweden)

    Egorov I.

    2017-11-01

    Full Text Available The results of the study of the provisions of the Federal Law "On Independent Qualification Assessment", of an explanatory note to the draft of the Federal Law "On Independent Qualification Assessment", of a number of other normative legal acts regarding the objectives and procedure for the implementation of an independent assessment of qualifications, including a professional exam, the use of its results, are described. On the basis of the analysis of a number of research works on the improvement of the qualifications of employees and the development of the system of continuous education, conclusions were drawn on an objective assessment by the legislator of a permanent increase in the requirements for the qualification of workers and the consequent need for continuous improvement of their qualifications, including the development of a continuous education system. Proposals have been formulated to introduce amendments to the legislation of the Russian Federation aimed at forming a recommendation for an employee to select existing resources for the self-alignment of an individual set of competences with a personalized offer of support options from the educational and professional structures - the trajectory of improving the qualification of an employee..

  16. Qualification Requirement Perceptions of the United States Army Acquisition Workforce Since Implementation of the Defense Acquisition Workforce Improvement Act (DAWIA)

    Science.gov (United States)

    2013-12-01

    for the sake of learning is not the end, but only the means to an end ( Newman , 1947). The end is more about job impact and actual business results...requirements to what skills the employee actually needs to perform their job. The current cookie-cutter style of training requirements is a...acquisition process on the whole for large scale projects/programs. Acq. Level 2.5(B) - Based on the Parent program the employee works for and

  17. Review of qualifications for fuel assembly fabrication

    International Nuclear Information System (INIS)

    Slabu, Dan; Zemek, Martin; Hellwig, Christian

    2013-01-01

    The required quality of nuclear fuel in industrial production can only be assured by applying processes in fabrication and inspection, which are well mastered and have been proven by an appropriate qualification. The present contribution shows the understanding and experiences of Axpo with respect to qualifications in the frame of nuclear fuel manufacturing and reflects some related expectations of the operator. (orig.)

  18. Chapter No.8. Personnel qualification and training

    International Nuclear Information System (INIS)

    2002-01-01

    The overall training system and the development projects of training the staff of all categories from NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce were the subject of UJD's attention. During 2001 following inspections were carried out on nuclear personnel training: - PP's Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff; - Mochovce NPP: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; - SE-VYZ: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff. Training the staff of the NPP's Bohunice: - The fundamental and periodical theoretical training as sure as the fundamental and periodical simulator training is carried out by the VUJE Training centre in Trnava. - The fundamental practical training in the workplace and training for the change work- rank is carried at Bohunice plant. Training of the staff of the NPP Mochovce: - The fundamental and periodical theoretical training is carried out by the VUJE Training centre in Trnava. The fundamental practical training in the workplace and training for the change work- rank as well as the fundamental and periodical simulator training is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues a certificate on special professional skills of selected staff members of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: 1. Scientific shift manager for start up with the right of manipulation; 2. Shift supervisor; 3. Unit supervisor; 4. Primary circuit operator; 5. Secondary circuit operator; 6. Reactor physicist; 7. Scientific shift manager for start up without the right of manipulation. Examinations of

  19. Requirements for facilities transferring or receiving select agents. Final rule.

    Science.gov (United States)

    2001-08-31

    CDC administers regulations that govern the transfer of certain biological agents and toxins ("select agents"). These regulations require entities that transfer or receive select agents to register with CDC and comply with biosafety standards contained in the Third Edition of the CDC/NIH publication "Biosafety in Microbiological and Biomedical Laboratories ("BMBL")." On October 28,1999, CDC published a Notice of Proposed Rulemaking ("NPRM") seeking both to revise the biosafety standards facilities must follow when handling select agents and to provide new biosecurity standards for such facilities. These new standards are contained in the Fourth Edition of BMBL, which the NPRM proposed to incorporate by reference, thereby replacing the Third Edition. No comments were received in response to this proposal. CDC is therefore amending its regulations to incorporate the Fourth Edition.

  20. 45 CFR 2522.950 - What requirements and qualifications apply if my program focuses on supplemental academic support...

    Science.gov (United States)

    2010-10-01

    ... program focuses on supplemental academic support activities other than tutoring? 2522.950 Section 2522.950... support activities other than tutoring? (a) If your program does not involve tutoring as defined in § 2522... SERVICE AMERICORPS PARTICIPANTS, PROGRAMS, AND APPLICANTS Program Management Requirements for Grantees...

  1. 49 CFR 1103.3 - Persons not attorneys-at-law-qualifications and requirements for practice before the Board.

    Science.gov (United States)

    2010-10-01

    ... burden of proof is on the applicant to establish that the formal education satisfies the standards set... standards. A non-attorney applicant for admission to practice must meet one of the following requirements... secondary education and must possess technical knowledge, training or experience in the field of...

  2. 14 CFR 121.453 - Flight engineer qualifications.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Flight engineer qualifications. 121.453... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Crewmember Qualifications § 121.453 Flight engineer qualifications. (a) No certificate holder may use any person nor may any person serve as a flight engineer on an...

  3. Safety review for seismic qualification on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Fang Qingxian

    1995-01-01

    The standards and requirements for seismic qualification of nuclear power plant's component have been fully addressed, including the scope of seismic qualification, the approach and the method of common seismic qualification, the procedure of the seismic tests, and the criteria for the seismic qualification review. The problems discovered in the safety review and the solution for these problems and some other issues are also discussed

  4. SATISFACTION OF QUALIFICATION REQUIREMENTS OF EMPLOYERS APPLIED TO SOFTWARE ENGINEERS IN THE PROCESS OF TRAINING AT HIGHER EDUCATIONAL INSTITUTIONS

    Directory of Open Access Journals (Sweden)

    Vladislav Kruhlyk

    2017-03-01

    Full Text Available In the article, based on the analysis of the problems of the professional training of software engineers in higher educational institutions, was shown that the contents of the curricula for the training of software engineers in basic IT specialties in higher education institutions generally meet the requirements to them at the labor market. It is stated that at the present time there are certain changes in the job market not only in the increasing demand for IT professionals but also in the requirements settled for future specialists. To scientists’ opinion, at present there is a gap between the level of expectation of employers and the level of education of graduates of IT-specialties of universities. Due to the extremely fast pace of IT development, already at the end of the studies, students' knowledge may become obsolete. We are talking about a complex of competencies offered by university during training of specialist for their relevance and competitiveness at the labor market. At the same time, the practical training of students does not fully correspond to the current state of information technology. Therefore, it is necessary to ensure the updating of the contents of the academic disciplines with the aim of providing quality training of specialists.

  5. Environmental/dynamic mechanical equipment qualification and dynamic electrical equipment qualification program (EDQP)

    International Nuclear Information System (INIS)

    Hunter, J.A.

    1984-01-01

    Equipment qualification research is being conducted to investigate acceptable criteria, requirements, and methodologies for the dynamic (including seismic) and environmental qualification of mechanical equipment and for the dynamic (including seismic) qualification of electrical equipment. The program is organized into three elements: (1) General Research, (2) Environmental Research, and (3) Dynamic Research. This paper presents the highlights of the results to date in these three elements of the program

  6. Radiation Safety (Qualifications) Regulations 1980

    International Nuclear Information System (INIS)

    1980-01-01

    These Regulations, promulgated pursuant to the provisions of the Radiation Safety Act, 1975-1979, require persons engaged in activities involving radiation to pass a radiation safety examination or to possess an approved qualification in radiation. The National Health and Medical Research Council is authorised to exempt persons from compliance with these requirements or, conversely, to impose such requirements on persons other than those designated. (NEA) [fr

  7. Power system requirements and selection for the space exploration initiative

    International Nuclear Information System (INIS)

    Biringer, K.L.; Bartine, D.E.; Buden, D.; Foreman, J.; Harrison, S.

    1991-01-01

    The Space Exploration Initiative (SEI) seeks to reestablish a US program of manned and unmanned space exploration. The President has called for a program which includes a space station element, a manned habitation of the moon, and a human exploration of Mars. The NASA Synthesis Group has developed four significantly different architectures for the SEI program. One key element of a space exploration effort is the power required to support the missions. The Power Speciality Team of the Synthesis Group was tasked with assessing and evaluating the power requirements and candidate power technologies for such missions. Inputs to the effort came from existing NASA studies as well as other governments agency inputs such as those from DOD and DOE. In addition, there were industry and university briefings and results of solicitations from the AIAA and the general public as part of the NASA outreach effort. Because of the variety of power needs in the SEI program, there will be a need for multiple power system technologies including solar, nuclear and electrochemical. Due to the high rocket masses required to propel payloads to the moon and beyond to Mars, there is great emphasis placed on the need for high power density and high energy density systems. Power system technology development work is needed results will determine the ultimate technology selections. 23 refs., 10 figs

  8. Appointment, qualifications and responsibilities of ventilation officers

    International Nuclear Information System (INIS)

    1981-01-01

    The Code provides for the appointment of a ventilation officer when required by the appropriate authority. This guideline offers comment on the appointment, qualifications, training and responsibilities of that person

  9. Emergency Management. Functional Area Qualification Standard

    National Research Council Canada - National Science Library

    2004-01-01

    .... In support of this goal, the competency requirements defined in the Technical Qualification Standards should be aligned with and integrated into the recruitment and staffing processes for technical positions...

  10. Qualification of organizations for independent technical supervision

    International Nuclear Information System (INIS)

    1981-04-01

    The requirements are established on trial for the qualification of an organization as an independent technical supervision organization in nuclear facilities, in activities related with quality assurance programs. (I.C.R.) [pt

  11. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2001-01-01

    The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

  12. TOUGH2 software qualification

    International Nuclear Information System (INIS)

    Pruess, K.; Simmons, A.; Wu, Y.S.; Moridis, G.

    1996-02-01

    TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. It belongs to the MULKOM (open-quotes MULti-KOMponentclose quotes) family of codes and is a more general version of the TOUGH simulator. The MULKOM family of codes was originally developed with a focus on geothermal reservoir simulation. They are suited to modeling systems which contain different fluid mixtures, with applications to flow problems arising in the context of high-level nuclear waste isolation, oil and gas recovery and storage, and groundwater resource protection. TOUGH2 is essentially a subset of MULKOM, consisting of a selection of the better tested and documented MULKOM program modules. The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of TOUGH2

  13. TOUGH2 software qualification

    Energy Technology Data Exchange (ETDEWEB)

    Pruess, K.; Simmons, A.; Wu, Y.S.; Moridis, G.

    1996-02-01

    TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. It belongs to the MULKOM ({open_quotes}MULti-KOMponent{close_quotes}) family of codes and is a more general version of the TOUGH simulator. The MULKOM family of codes was originally developed with a focus on geothermal reservoir simulation. They are suited to modeling systems which contain different fluid mixtures, with applications to flow problems arising in the context of high-level nuclear waste isolation, oil and gas recovery and storage, and groundwater resource protection. TOUGH2 is essentially a subset of MULKOM, consisting of a selection of the better tested and documented MULKOM program modules. The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of TOUGH2.

  14. Nuclear security personnel for power plants. Content and review procedures for a security training and qualification program

    International Nuclear Information System (INIS)

    1978-06-01

    The applicant and licensee training and qualification plans will outline the process by which guard, watchman, armed response persons and other members of the security organization will be selected, trained, equipped and qualified. This plan should contain: (1) job descriptions for all security positions; (2) duties defined for all positions; (3) critical tasks defined for all duties; (4) skills, knowledge and abilities defined for all critical tasks; (5) performance objectives stated for all critical tasks; and (6) training and qualification plans to train and test to appropriate performance objectives. The document gives guidance on the preparation of this training and qualification plan and contains three parts: (1) an introduction to and brief explanation of job analysis and performance objectives; (2) a statement of the information that should be submitted in response to the requirements and the NRR review procedures; and (3) a sample qualification submittal

  15. Qualification of NDT systems for in-service inspections of nuclear power plant pressure vessels

    International Nuclear Information System (INIS)

    Elfving, K.

    1998-11-01

    The goal of this study is to determine the requirements of the in-service inspection qualification in Europe, their feasibility in practice and to find out possible manufacture defects in test pieces used in practical trials. The literature study consists of qualification requirements set by European regulatory bodies and by the European nuclear power utilities. Also a brief summary of qualification requirements set by ASME Code, Section XI and comparison between ASME and European qualification requirements is included

  16. Nuclear Criticality Safety Department Qualification Program

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

  17. Materials qualification for nuclear power plants

    International Nuclear Information System (INIS)

    Braconi, F.

    1987-01-01

    The supply of materials to be used in the fabrication of components submitted to pressure destined to Atucha II nuclear power plant must fulfill the quality assurance requirements in accordance with the international standards. With the aim of promoting the national participation in CNA II, ENACE had the need to adapt these requirements to the national industry conditions and to the availability of official entities' qualification and inspection. As a uniform and normalized assessment for the qualification of materials did not exist in the country, ENACE had to develop a materials suppliers qualification system. This paper presents a suppliers qualification procedure, its application limits and the alternative procedures for the acceptance of individual stock and for the stock materials purchase. (Author)

  18. Electrical equipment qualification

    International Nuclear Information System (INIS)

    Farmer, W.S.

    1983-01-01

    Electrical equipment qualification research programs being carried out by CEA, JAERI, and Sandia Laboratories are discussed. Objectives of the program are: (1) assessment of accident simulation methods for electrical equipment qualification testing; lower coarse (2) evaluation of equipment aging and accelerated aging methods; (3) determine radiation dose spectrum to electrical equipment and assess simulation methods for qualification; (4) identify inadequacies in electrical equipment qualification procedures and standards and potential failure modes; and (5) provide data for verifying and improving standards, rules and regulatory guides

  19. Preliminary Hanford Waste Vitrification Plan Waste Form Qualification Plan

    International Nuclear Information System (INIS)

    Nelson, J.L.

    1987-09-01

    This Waste Form Qualification Plan describes the waste form qualification activities that will be followed during the design and operation of the Hanford Waste Vitrification Plant to ensure that the vitrified Hanford defense high-level wastes will meet the acceptance requirements of the candidate geologic repositories for nuclear waste. This plan is based on the defense waste processing facility requirements. The content of this plan is based on the assumption that the Hanford Waste Vitrification Plant high-level waste form will be disposed of in one of the geologic repository projects. Proposed legislation currently under consideration by Congress may change or delay the repository site selection process. The impacts of this change will be assessed as details of the new legislation become available. The Plan describes activities, schedules, and programmatic interfaces. The Waste Form Qualification Plan is updated regularly to incorporate Hanford Waste Vitrification Plant-specific waste acceptance requirements and to serve as a controlled baseline plan from which changes in related programs can be incorporated. 10 refs., 5 figs., 5 tabs

  20. Qualification of safety-related valve actuators

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This Standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. It may also be used to separately qualify actuator components. This Standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of all safety-related functions of power-driven valve actuators

  1. Safety design guides for environmental qualification for CANDU 9

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

    1996-03-01

    This safety design guide describes the safety philosophy and requirements for the environmental qualification of safety related systems and components for CANDU 9. The environmental qualification program identifies the equipments to be qualified and conditions to be used for qualification and provides comprehensive set of documentation to ensure that the qualification is complete and can be maintained for the life of the plant. A summary of the system, components and structures requiring environmental qualification is provided in the table for the guidance of the system design, and this table will be subject to change or confirmation by the environmental qualification program. Also, plant ares subject to harsh environment is provided in the figure. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 tab., 5 figs. (Author) .new

  2. Equipment qualification testing - a practical approach

    International Nuclear Information System (INIS)

    Davies, G.A.; McDougall, R.I.; Poirier, M.P.

    1996-01-01

    When nuclear safety equipment is credited with a Required Safety Function it must properly perform that function to facilitate safe control and/or shutdown of the plant during a design basis accident. When such equipment is required to be environmentally (EQ) and/or seismically qualified (SQ) for safety related use in CANDU nuclear power plants, the preferred method of qualification is by type testing. The qualification testing process requires that the test specimen equipment be subjected to the aging stressors associated with the normal service conditions that it would experience during it's required qualified (or service) life. Following the aging process, the test specimen is in a condition representative of that in which it would be at the end of its service life in the plant. The test specimen is then subjected to a simulated accident during which it must satisfy performance requirements thereby demonstrating that it can perform its required safety function. The performance requirements specified for the qualification testing must be designed to ensure that satisfactory performance of the safety function is demonstrated during the qualification program. This paper provides descriptions of practical methods used in the deriving and satisfying of relevant performance requirements during the qualification testing of safety related equipment. (author)

  3. Qualification and certification in NDT

    International Nuclear Information System (INIS)

    Hassan Kavarodi Maracair

    2003-01-01

    Ruane-TATI Sdn Bhd was the first accredited training centre in Asia approved by The British Institute of Non Destructive Testing (BINDT) as per EN 473, ISO 9712 and EN 45013 requirements. Meanwhile, Ruane-TATI is also accredited by National Vocational Training Center ( MLVK ).This mean that Ruane-TATI is the first training and examination center that accredited by both international and national bodies in providing quality , qualification and certification for comprehensive training and examination in Inspection and Non Destructive Testing (NDT). There are several NDT examinations scheme available in Malaysia due to differences requirement from the industrials. This has put the difficulties to services company in upgrading their NDT technician qualifications. The intention of this paper is to discuss the basic different among the NDT examinations scheme used in Malaysia ( mostly offered by Ruane-TATI ) and the development of certain schemes in covering their schemes to more sectors and NDT methods. (Author)

  4. Maintenance and environmental qualification

    International Nuclear Information System (INIS)

    Martin, R.S.; Austin, D.G.

    1995-01-01

    The design of today's nuclear generating plants involves many detailed design considerations. This includes comprehensive look at aging effects on plant components over their expected lifetimes. This is important to ensuring that the plant operates safely throughout its life. The effects of aging are required to be documented in detail in today's designs. This documentation provides assurance that safe operating conditions are maintained throughout the station life cycle. This requirement is analogous to the longer standing requirement to ensure pressure boundary integrity. The pressure boundary integrity requirement has existed in the industry since its inception. The subject of plant aging effects and the maintenance of functionality is known as Environmental Qualification (EQ). This paper will attempt to explain the wisdom of EQ and the potential for optimizing maintenance activities (to move from reactive to proactive activities), within the context of the overall maintenance program. It is the author's intent to encourage the active involvement of maintenance professionals in the effective implementation of the ongoing EQ program so that the benefits are maximized

  5. 14 CFR 125.285 - Pilot qualifications: Recent experience.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualifications: Recent experience... Requirements § 125.285 Pilot qualifications: Recent experience. (a) No certificate holder may use any person, nor may any person serve, as a required pilot flight crewmember unless within the preceding 90...

  6. Inspector qualification guidelines

    International Nuclear Information System (INIS)

    Batty, A.C.; Van Binnebeek, J.J.; Ericsson, P.O.; Fisher, J.C.; Geiger, P.; Grandame, M.; Grimes, B.K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

    1994-07-01

    The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied

  7. Inspector qualification guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Batty, A. C.; Van Binnebeek, J. J.; Ericsson, P. O.; Fisher, J. C.; Geiger, P.; Grandame, M.; Grimes, B. K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

    1994-07-15

    The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied.

  8. Approach to customer qualification of the BNFL Sellafield Mox Plant

    International Nuclear Information System (INIS)

    Sullivan, P.

    2003-01-01

    BNFL started plutonium commissioning of its Sellafield MOX Plant (SMP) in December 2001, with the first MOX pellets being produced in May 2002. SMP was designed to manufacture a range of both PWR and BWR fuel types for a number of different customers. During commissioning and early MOX fuel manufacturing BNFL has been demonstrating its ability to both automatically manufacture and inspect MOX fuel to meet the requirements of different customers' specifications and fuel types. The qualification project consisted of common and project specific qualification. Common qualification was carried out to demonstrate BNFL could meet several customers' requirements during the same qualification test. Project specific qualification was carried out for one customer only as the fabrication or inspection equipment was specific to their fuel type. An example is the fuel assembly process. The reasons for BNFL carrying out common qualification were: - Develop a common qualified process to meet different customer specifications. - Minimise future qualifications prior to starting future fuel campaigns. - Ensure BNFL understands and effectively manages different customer requirements in SMP. BNFL has approached qualification of SMP systematically. Firstly the inspection system was qualified, and once completed the inspection system was then used in the qualification of the manufacturing process. (orig.)

  9. Synapsin Is Selectively Required for Anesthesia-Sensitive Memory

    Science.gov (United States)

    Knapek, Stephan; Gerber, Bertram; Tanimoto, Hiromu

    2010-01-01

    Odor-shock memory in "Drosophila melanogaster" consists of heterogeneous components each with different dynamics. We report that a null mutant for the evolutionarily conserved synaptic protein Synapsin entails a memory deficit selectively in early memory, leaving later memory as well as sensory motor function unaffected. Notably, a consolidated…

  10. Establishment of nuclear equipment qualification system

    International Nuclear Information System (INIS)

    Joo, Po Kook; Lim, Nam Jin; Lee, Young Gun

    2003-04-01

    This study is carried out by KEARI(Korea Atomic Energy Research Institute) as the lead organization in cooperation with KIMM(Korea Institute of Machinery and Materials), KTL(Korea Testing Laboratory) and KRISS(Korea Research Institute of Standards and Science) to construct a basis of efficient management of nuclear equipment qualification business by expanding test equipment of each of participating organization, and developing qualification technologies. As for KIMM, control system of large scale shaker was replaced with advanced system, and LOCA(Loss of Coolant Accident) test facility was installed. KTL is now capable of conducting seismic tests of nuclear I and C as a result of installation of seismic test equipment during the first two project years. KRISS participated in the Project with a view to have large scale EMI test equipment and related technologies. In parallel with expansion of test equipment, a industrial-educational-research cooperation committee, as an intermediate step toward integrated equipment qualification system to maximize the usage of test equipment, was established and cooperation methods were investigated. As a result, Korea Nuclear Equipment Qualification Association, an corporate juridical person, was established. Research on development of thermal and radiation aging test technology of nuclear materials was carried out by Hanyang University and SECO(Saehan Engineering and Qualification Co., Ltd.). Integrated Equipment Qualification Database was developed which contains material test data, equipment qualification data and other EQ related informations. Standard qualification procedures were developed in order for test laboratories and manufacturers to establish design requirements and to efficiently perform tests

  11. Seismic qualification of existing nuclear installations in India - a proposal

    International Nuclear Information System (INIS)

    Basu, P.C.

    2001-01-01

    In India, the work toward seismic qualification of existing nuclear facilities has been started. Preliminary work is being undertaken with respect to identifying the facilities which would be taken up for seismic qualification, approach and methodology for re-evaluation for seismic safety, acceptance criteria, etc. Work has also been started for framing up the criteria and methodology of the seismic qualification of these facilities. Present paper contains the proposal in this respect. This proposal is on similar lines of the present practice of seismic qualification of NPP, as summarized in the Appendix, but has been modified to suit the special requirements of Indian nuclear installations. (author)

  12. The qualification of reactor operators

    International Nuclear Information System (INIS)

    Lima, J.M. de; Soares, H.V.

    1981-01-01

    The qualification and performance of nuclear power personnel have an important influence on the availability and safety operation of these plants. This paper describes the Brazilian rules and norms established by the CNEN-Brazilian Atomic Energy Comission, as well as policy of other countries concerning training requirements and experiences of nuclear power reactor operators. Some coments are made about the im pact of the march 1979 Three Mile Island accident on upgrading the reactor training requirements in U.S.A. and its international implication. (Author) [pt

  13. 47 CFR 80.225 - Requirements for selective calling equipment.

    Science.gov (United States)

    2010-10-01

    ... Commission will not accept new applications (but will continue to process then-pending applications) for certification of non-portable DSC equipment that does not meet the requirements of ITU-R Recommendation M.493-11... Commission will not accept new applications (but will continue to process then-pending applications) for...

  14. Qualification of ISI for Bulgarian NPP: UK support

    International Nuclear Information System (INIS)

    Booler, R.

    2000-01-01

    UK Regulator (NII) Phare project provides an assistance to the Bulgarian Regulator in setting up the technical infrastructure for inspection qualification consistent with IAEA Guidelines and western European practice. The Strategy Document defines the methodology for inspection qualification and general roles and responsibilities of the involved organizations. The Qualification Inputs Document describes the information required for the Technical Specifications (component details, inspection aims and limitations). It applies the idea of qualification level - level 1(lowest) to level 3 (highest). The Qualification Procedure Document provides a guidance to the utility ('Kozloduy' NPP) on the preparation of Qualification Procedures (QP). The appendix provides a specific guidance on the performance of the all aspects of qualification at different levels and recommendations for technical justification. QB Method Working Document provides guidance for the Qualification Body. Facilities and Resources Document defines the facilities and resources required for the Qualification Body to perform the tasks described in the Method Working Document. High level QA Document defines the principles of quality control. Other issues and progress report are also presented

  15. On Propagating Requirements and Selecting Fuels for a Benson Boiler

    DEFF Research Database (Denmark)

    Kragelund, Martin Nygaard; Wisniewski, Rafal; Mølbak, Tommy

    2008-01-01

    In this paper, the problem of optimal choice of sensors and actuators is addressed. Given a functional encapsulating information of the desired performance and production economy the objective is to choose a control instrumentation from a given set to comply with its minimum. The objective of the...... to propagate a global objective to local subsystems. Particular focus is on a boiler in a power plant operated by Dong Energy. The business objectives have been propagated to the actuator level to allow for selection of an actuator configuration....

  16. Radiological Control Technician: Standardized technician Qualification Standard

    International Nuclear Information System (INIS)

    1992-10-01

    The Qualification Standard states and defines the knowledge and skill requirements necessary for successful completion of the Radiological Control Technician Training Program. The standard is divided into three phases: Phase I concerns RCT Academic training. There are 13 lessons associated with the core academics program and 19 lessons associated with the site academics program. The staff member should sign the appropriate blocks upon successful completion of the examination for that lesson or group of lessons. In addition, facility specific lesson plans may be added to meet the knowledge requirements in the Job Performance Measures (JPM) of the practical program. Phase II concerns RCT core/site practical (JPMs) training. There are thirteen generic tasks associated with the core practical program. Both the trainer/evaluator and student should sign the appropriate block upon successful completion of the JPM. In addition, facility specific tasks may be added or generic tasks deleted based on the results of the facility job evaluation. Phase III concerns the oral examination board successful completion of the oral examination board is documented by the signature of the chairperson of the board. Upon completion of all of the standardized technician qualification requirements, final qualification is verified by the student and the manager of the Radiological Control Department and acknowledged by signatures on the qualification standard. The completed Qualification Standard shall be maintained as an official training record

  17. Establishment of coral-algal symbiosis requires attraction and selection.

    Directory of Open Access Journals (Sweden)

    Hiroshi Yamashita

    Full Text Available Coral reef ecosystems are based on coral-zooxanthellae symbiosis. During the initiation of symbiosis, majority of corals acquire their own zooxanthellae (specifically from the dinoflagellate genus Symbiodinium from surrounding environments. The mechanisms underlying the initial establishment of symbiosis have attracted much interest, and numerous field and laboratory experiments have been conducted to elucidate this establishment. However, it is still unclear whether the host corals selectively or randomly acquire their symbionts from surrounding environments. To address this issue, we initially compared genetic compositions of Symbiodinium within naturally settled about 2-week-old Acropora coral juveniles (recruits and those in the adjacent seawater as the potential symbiont source. We then performed infection tests using several types of Symbiodinium culture strains and apo-symbiotic (does not have Symbiodinium cells yet Acropora coral larvae. Our field observations indicated apparent preference toward specific Symbiodinium genotypes (A1 and D1-4 within the recruits, despite a rich abundance of other Symbiodinium in the environmental population pool. Laboratory experiments were in accordance with this field observation: Symbiodinium strains of type A1 and D1-4 showed higher infection rates for Acropora larvae than other genotype strains, even when supplied at lower cell densities. Subsequent attraction tests revealed that three Symbiodinium strains were attracted toward Acropora larvae, and within them, only A1 and D1-4 strains were acquired by the larvae. Another three strains did not intrinsically approach to the larvae. These findings suggest the initial establishment of corals-Symbiodinium symbiosis is not random, and the infection mechanism appeared to comprise two steps: initial attraction step and subsequent selective uptake by the coral.

  18. Required experimental accuracy to select between supersymmetrical models

    Science.gov (United States)

    Grellscheid, David

    2004-03-01

    We will present a method to decide a priori whether various supersymmetrical scenarios can be distinguished based on sparticle mass data alone. For each model, a scan over all free SUSY breaking parameters reveals the extent of that model's physically allowed region of sparticle-mass-space. Based on the geometrical configuration of these regions in mass-space, it is possible to obtain an estimate of the required accuracy of future sparticle mass measurements to distinguish between the models. We will illustrate this algorithm with an example. This talk is based on work done in collaboration with B C Allanach (LAPTH, Annecy) and F Quevedo (DAMTP, Cambridge).

  19. Qualification of nuclear power plant operations personnel

    International Nuclear Information System (INIS)

    1984-01-01

    With the ultimate aim of reducing the possibility of human error in nuclear power plant operations, the Guidebook discusses the organizational aspects, the staffing requirements, the educational systems and qualifications, the competence requirements, the ways to establish, preserve and verify competence, the specific aspects of personnel management and training for nuclear power plant operations, and finally the particular situations and difficulties to be overcome by utilities starting their first nuclear power plant. An important aspect presented in the Guidebook is the experience in training and qualification of nuclear power plant personnel in various countries: Argentina, Belgium, Canada, Czechoslovakia, France, Federal Republic of Germany, Spain, Sweden, United Kingdom and United States of America

  20. 14 CFR 135.247 - Pilot qualifications: Recent experience.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualifications: Recent experience... Flight Crewmember Requirements § 135.247 Pilot qualifications: Recent experience. (a) No certificate holder may use any person, nor may any person serve, as pilot in command of an aircraft carrying...

  1. 14 CFR 121.439 - Pilot qualification: Recent experience.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Recent experience. 121... Pilot qualification: Recent experience. (a) No certificate holder may use any person nor may any person serve as a required pilot flight crewmember, unless within the preceding 90 days, that person has made...

  2. 12 CFR 563c.3 - Qualification of public accountant.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Qualification of public accountant. 563c.3... REQUIREMENTS Form and Content of Financial Statements § 563c.3 Qualification of public accountant. (See also 17 CFR 210.2-01.) The term “qualified public accountant” means a certified public accountant or licensed...

  3. 29 CFR 1926.1076 - Qualifications of dive team.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 8 2010-07-01 2010-07-01 false Qualifications of dive team. 1926.1076 Section 1926.1076 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION... § 1926.1076 Qualifications of dive team. Note: The requirements applicable to construction work under...

  4. 29 CFR 1910.410 - Qualifications of dive team.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 5 2010-07-01 2010-07-01 false Qualifications of dive team. 1910.410 Section 1910.410... Requirements § 1910.410 Qualifications of dive team. (a) General. (1) Each dive team member shall have the experience or training necessary to perform assigned tasks in a safe and healthful manner. (2) Each dive team...

  5. 14 CFR 121.909 - Approval of Advanced Qualification Program.

    Science.gov (United States)

    2010-01-01

    ... criteria. Each AQP must have separate curriculums for indoctrination, qualification, and continuing... the training and evaluation of CRM and technical skills and knowledge. An application for approval of... must meet all the requirements of this subpart. (2) Each indoctrination, qualification, and continuing...

  6. Selection criteria and requirements for floors in nuclear facilities

    International Nuclear Information System (INIS)

    Kunze, S.

    1988-01-01

    As a surface protection of floors in nuclear facilities coatings, rubber and PVC coverings, respectively, are normally used, whereas stoneware tiles are still provided in rare cases only. All floor materials must be well decontaminable according to the German standard DIN 25415, Part 1. The general requirement is that low-porous, smooth products with little filler content, made of chemically resistant material, are very well decontaminable. Further investigations will be necessary for heavily loaded floor coatings. They include above all examinations for decontaminability after radiation and for wear and resistance to chemicals. These requirements have been compiled in DIN 55991. The examination of about 212 industrial products has revealed that the decontaminability of covering materials is frequently poor. Investigations have shown that the decontaminability is always deteriorated by additions of hygroscopic fillers. Additions of non-hygroscopic fillers and pigments may result in an excellent to poor decontaminability. The pore-free bonding of the covering materials by welding or jointing is of great importance with respect to the decontaminability of these floors. Care should be taken that the jointing compounds are as well decontaminable as the rubber coverings and stonewares. (orig.) [de

  7. Selection criteria and requirements for floors in nuclear plants

    International Nuclear Information System (INIS)

    Kunze, S.

    1987-01-01

    As a surface protection of floors in nuclear facilities coatings, rubber and PVC coverings, respectively, are normally used, whereas stoneware tiles are still provided in rare cases only. All floor materials must be well decontaminable according to the German standard DIN 25415, Part 1. The general requirement is that low-porous, smooth products with little filler content, made of chemically resistant material, are very well decontaminable. Further investigations will be necessary for heavily loaded floor coatings. They include above all examinations for decontaminability after radiation and for wear and resistance to chemicals. These requirements have been compiled in DIN 55991. The examination of about 200 industrial products has revealed that the decontaminability of covering materials is frequently poor. Investigations have shown that the decontaminability is always deteriorated by additions of hygroscopic fillers. Additions of non-hygroscopic fillers and pigments may result in an excellent to poor decontaminability. The pore-free bonding of the covering materials by welding or jointing is of great importance with respect to the decontaminability of these floors. Care should be taken that the jointing compounds are as well decontaminable as the rubber coverings and stonewares. (orig.) [de

  8. Nitrogen requirements of cassava in selected soils of Thailand

    Directory of Open Access Journals (Sweden)

    Jakchaiwat Kaweewong

    2013-08-01

    Full Text Available Cassava (Manihot esculenta is one of the most important export crops in Thailand, yet the nitrogen requirement is unknown and not considered by growers and producers. Cassava requirements for N were determined in field experiments during a period of four years and four sites on the Satuk (Suk, Don Chedi (Dc, Pak Chong (Pc,and Ban Beung (BBg soil series in Lopburi, Supanburi, Nakhon Ratchasima, and Chonburi sites, respectively. The fertilizer treatment structure comprised 0, 62.5, 125, 187.5, 250 and 312.5 kg N ha^(-1 as urea. At each site cassava was harvested at nine months and yield parameters and the minimum datasets were taken. The fertilizer rate which resulted in maximum yield ranged from 187.5 kg N ha^(-1 in Supanburi and Chonburi (fresh weight yield of 47,500 and 30,000 kg ha^(-1 respectively to 250 kg N ha^(-1 in Lopburi and Nakhon Ratchasima (fresh weight yield of 64,100 and 46,700 kg ha^(-1 respectively. Yield appeared to decrease at the higher, 312 kg ha^(-1, at Supanburi and Lopburi, and 250 kg ha^(-1 (Chonburi fertilizer N rates. Net revenue was 70.4 and 72.9 % higher than where no N was appliedLopburi and Nakhon Ratchasima sites. Net revenue at the Supanburi and Chonburi sites were 53.8 and 211.0 % higher than that where no N was applied. This study suggests that at all sites improved cassava production and net revenue could be obtained with the judicious application of higher quantities of N. The results provide needed guidance to nitrogen fertilization of the important industrial crop cassava in Thailand.

  9. Mean-Variance Portfolio Selection with Margin Requirements

    Directory of Open Access Journals (Sweden)

    Yuan Zhou

    2013-01-01

    Full Text Available We study the continuous-time mean-variance portfolio selection problem in the situation when investors must pay margin for short selling. The problem is essentially a nonlinear stochastic optimal control problem because the coefficients of positive and negative parts of control variables are different. We can not apply the results of stochastic linearquadratic (LQ problem. Also the solution of corresponding Hamilton-Jacobi-Bellman (HJB equation is not smooth. Li et al. (2002 studied the case when short selling is prohibited; therefore they only need to consider the positive part of control variables, whereas we need to handle both the positive part and the negative part of control variables. The main difficulty is that the positive part and the negative part are not independent. The previous results are not directly applicable. By decomposing the problem into several subproblems we figure out the solutions of HJB equation in two disjoint regions and then prove it is the viscosity solution of HJB equation. Finally we formulate solution of optimal portfolio and the efficient frontier. We also present two examples showing how different margin rates affect the optimal solutions and the efficient frontier.

  10. Definitions, qualifications and requirements for radiation protection experts, radiation protection officers and radiation workers: results of the 2 nd EUTERP Workshop

    International Nuclear Information System (INIS)

    Draaisma, Folkert S.; Steen, Jan van der

    2008-01-01

    Full text: In Europe, a common vision for maintaining competence in radiation protection is emerging, focussing on a common denominator for qualification of radiation protection experts (RPEs) and radiation protection officers (RPOs) and for mutual recognition and mobility of these professionals across the European Union. Therefore, the European Commission, D.-G. Transport and Energy, has launched an initiative to establish a European Radiation Protection Training and Education Platform (EUTERP Platform). The objectives of the Platform can be summarised as: to facilitate the trans national access to vocational education and training; to better integrate education and training into occupational radiation protection infrastructures in the Member, Candidate and Associated States of the European Union. The Platform ensures a permanent dialogue between all involved parties by the use of its web site (www.euterp.eu), by issuing newsletters and by organising workshops. The first workshop has been held in Vilnius, 22-24 May 2007, and resulted in 8 recommendations to the European Commission, the IAEA, IRPA and national authorities. The recommendations were, a.o., dealing with: new definitions for the Radiation Protection Expert (RPE) and the Radiation Protection Officer (RPO), which should be used in the revision of both the EURATOM and the International BSS; developing guidance for a methodology to compare the quality of training courses and training material; developing guidance for a standardized methodology of assessing the recognition of RP professionals as a basis for future mutual recognition, based on a description of roles and duties, education, training and work experience; developing guidance for a formal recognition process of the competence of RPEs and RPOs. The second workshop will be held on 23-25 April 2008, again in Vilnius, and will specifically discuss the above-mentioned proposals for new definitions and guidance material. It is expected that the

  11. Implementation plans for the Korean certified tumor registrar qualification system.

    Science.gov (United States)

    Boo, Yoo-Kyung; Lim, Hyun-Sook; Won, Young-Joo

    2014-01-01

    Cancer registration data is used to understand the nation's cancer burden, and to provide significant baseline data for cancer control efforts, as well as, research on cancer incidence, mortality, survival, and prevalence. A system that approves, assesses, and manages the qualification of specialists, responsible for performing cancer registration, has not been developed in Korea. This study presents ways to implement a certification system designed for the qualification of tumor registrars in Korea. Requirements for implementing a certified tumor registrar qualification system were determined by reviewing the system for establishing qualifications in Korea and the American qualification system via the National Cancer Registrars Association (NCRA). Moreover, a survey was conducted on Korean medical records administrators, who had taken the U.S. Certified Tumor Registrar (CTR) examination, in order to review their opinions regarding these requirements. This study verified the feasibility of a qualification examination based on the opinions of CTR specialists by determining the following: items, and the associated ratings, of the qualifications necessary to register individuals as certified tumor registrars in a private qualification system; status of human resources required for the examination or training processes; plans regarding the organization needed for management, and operation of qualifications, examination standards, subject areas, examination methods, examination qualifications, or education and training programs. The implementation of a certified tumor registrar qualification system will lead to enhanced job competency for specialists and a qualitative improvement of cancer registration data. It will also reliably foster human resources that will lay the groundwork needed to establish scientific and reasonable national cancer management policies.

  12. Changing nature of equipment and parts qualification

    International Nuclear Information System (INIS)

    Bucci, R.M.

    1988-01-01

    Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace

  13. Unintended Consequences: How Qualification Constrains Innovation

    Science.gov (United States)

    Brice, Craig A.

    2011-01-01

    The development and implementation of new materials and manufacturing processes for aerospace application is often hindered by the high cost and long time span associated with current qualification procedures. The data requirements necessary for material and process qualification are extensive and often require millions of dollars and multiple years to complete. Furthermore, these qualification data can become obsolete for even minor changes to the processing route. This burden is a serious impediment to the pursuit of revolutionary new materials and more affordable processing methods for air vehicle structures. The application of integrated computational materials engineering methods to this problem can help to reduce the barriers to rapid insertion of new materials and processes. By establishing predictive capability for the development of microstructural features in relation to processing and relating this to critical property characteristics, a streamlined approach to qualification is possible. This paper critically examines the advantages and challenges to a modeling-assisted qualification approach for aerospace structural materials. An example of how this approach might apply towards the emerging field of additive manufacturing is discussed in detail.

  14. 10 CFR 50.76 - Licensee's change of status; financial qualifications.

    Science.gov (United States)

    2010-01-01

    ... the financial qualifications information that would be required for obtaining an initial operating license as specified in § 50.33(f)(2). The financial qualifications information must address the first... 10 Energy 1 2010-01-01 2010-01-01 false Licensee's change of status; financial qualifications. 50...

  15. Relationship Between Teachers\\' Qualification And Students ...

    African Journals Online (AJOL)

    It has been observed that students\\' performance in technical subjects is very poor. Coupled with this problem is that of lack of qualified technical teachers. This study determines the relationship between teachers\\' qualification and students\\' performance in technical subjects in selected schools in northern Nigeria.

  16. Qualification issues: the rest of the iceberg

    International Nuclear Information System (INIS)

    Bonzon, L.L.; Luna, R.E.

    1978-01-01

    Reactor safety has been a primary concern since the beginning of commercial power reactor development. But only since the IEEE became actively involved (circa-1970), through IEEE-323-1971 and its predecessor drafts, has the qualification of selected Class 1 equipment been formalized and intensified. Currently EPRI and the USNRC are funding significant qualification research programs. However, these current research topics address only a few of the issues and there are more to come. A review of recent achievements and a discussion of some issues still to be encountered are presented

  17. Qualification criteria for persons responsible for radiation protection

    International Nuclear Information System (INIS)

    Wehner, G

    1980-01-01

    A survey of the qualification criteria included in the German atomic law (Atomic Energy Act, Radiological Protection Ordinance and X-ray Protection Ordinance) for persons responsible for radiation protection is given. Especially the various activities for which a health physics officer is required, the range of qualification in each case and the way the qualification has to be proved, are pointed out. Also the different guides that are issued to complete the legal requirements are mentioned. The definitions of the term qualification for health physics given in the different guides are cited and it is shown, that the qualification of a healt physics officer has to be based on the three criteria (I) vocational training. (II) professional experience and (III) the necessary knowledge in radiation protection. (orig./HP) [de

  18. T25 Qualification of old containers

    International Nuclear Information System (INIS)

    Hoerning, T.; Kasparek, E.M.; Voelzke, H.

    2013-01-01

    Radioactive waste for final disposal in the repository Konrad has to be packaged in licensed containers. The qualification of containers is performed according the respective standards and BfS requirements. The latter ones differ for different container types with respect to accident resistance based on the release behavior of the waste. Usually qualification of container types is performed before series production. The qualification of already produced containers (''old containers'') is significantly more complicated. The differences of quality assurance and materials properties of the older containers have to be evaluated. A main tool for this evaluation is the numerical re-calculation of accident scenarios for estimation of the safety margins. The validation of appropriate finite element models is available. Based on these date it might be possible to abandon additional drop tests with the existing old containers to prove the structural integrity.

  19. 42 CFR 485.705 - Personnel qualifications.

    Science.gov (United States)

    2010-10-01

    ... Physical Therapy and Speech-Language Pathology Services § 485.705 Personnel qualifications. (a) General... involved in the furnishing of outpatient physical therapy, occupational therapy, and speech-language...) of the Act and the requirements in part 484 of this chapter. (2) For a speech-language pathologist...

  20. Dynamic testing and qualification

    International Nuclear Information System (INIS)

    Kleine Tebbe, A.; Schmidt, G.; Theymann, W.

    1990-01-01

    The core structure of an HTR-plant consists of the side reflector, the bottom reflector, the top reflector and the pebble bed of spherical fuel elements. Dynamically this system is a many-body structure with non-linear force-deformation couplings. The integrity of the system under seismic loads is given by radially orientated spring packs. These spring packs must be stiff against earthquake loads, but must allow radial thermal movements. To verify the seismic safety of the system, scaled-down models were tested. The results of these tests were compared with those of analytical methods. The good-natured behaviour of the pebble-bed under seismic loads has been confirmed. Due to the granular structure of the non-regular packed pebble-bed, high damping occurs during seismic excitations. With increasing depth the damping ratio decreases because of restriction of movement. We are able to describe the seismic behaviour of the pebble-bed analytically. The one- and two-dimensional test configurations of the top reflector were used to analyse resonance and lumping effects. The experimental results were verified by the computer codes CRUNCH-1D AND CRUNCH-2D. The experimental investigations of the side reflector are underway. The results show a non-critical behaviour under horizontal excitations. Small rigid-body motions of single blocks are detected, but they do not cause any global ovalisations of the complete ring structure. Finite element calculations with contact and friction between the blocks show a close agreement with the experimental results. Seismic qualification of ground mounted electrical equipment is usually performed on the basis of codes like IEEE, IEC, KTA, etc. These standards give different possibilities of the excitation mode: sinusoidal excitation in every natural frequency (continuous or sine beat) or time history excitation which covers a prescribed required response spectrum. Recently performed tests are compared regarding the usefulness and severity

  1. Qualification of a select one-stage activated partial thromboplastin time-based clotting assay and two chromogenic assays for the post-administration monitoring of nonacog beta pegol.

    Science.gov (United States)

    Tiefenbacher, S; Bohra, R; Amiral, J; Bowyer, A; Kitchen, S; Lochu, A; Rosén, S; Ezban, M

    2017-10-01

    Essentials Nonacog beta pegol (N9-GP) is an extended half-life, recombinant human factor IX (FIX). One-stage clotting (OSC) and chromogenic FIX activity assays were assessed for N9-GP recovery. OSC STA ® -Cephascreen ® , ROX FIX and BIOPHEN FIX chromogenic assays were qualified for N9-GP. Other extended half-life factor products should be assessed in a similar way prior to approval. Background Nonacog beta pegol (N9-GP) is an extended half-life, glycoPEGylated recombinant human factor IX that is under development for the prophylaxis and treatment of bleeding episodes in hemophilia B patients. Considerable reagent-dependent variability has been observed when one-stage clotting assays are used to measure the recovery of recombinant FIX products, including N9-GP. Objective To qualify select one-stage clotting and chromogenic FIX activity assays for measuring N9-GP recovery. Methods The accuracy and precision of the one-stage clotting assay (with the STA-Cephascreen activated partial thromboplastin [APTT] reagent) and the ROX Factor IX and BIOPHEN Factor IX chromogenic assays for measuring N9-GP recovery were assessed in N9-GP-spiked hemophilia B plasma samples in a systematic manner at three independent sites, with manufacturer-recommended protocols and/or site-specific assay setups, including different instruments. Results For each of the three FIX activity assays qualified on five different reagent-instrument systems, acceptable intra-assay and interassay accuracy and precision, dilution integrity, reagent robustness and freeze-thaw and short-term sample stabilities were demonstrated. The STA-Cephascreen assay showed a limited reportable range at one of the three qualification sites, and the BIOPHEN Factor IX assay showed suspect low-end sensitivity at one of the three qualification sites. An individual laboratory would account for these limitations by adjusting the assay's reportable range; thus, these findings are not considered to impact the respective

  2. Buried Waste Program (BWP) data qualification manual

    International Nuclear Information System (INIS)

    Casey, C.; Larson, R.A.; Harris, G.A.

    1989-06-01

    The Data Qualification Manual (DQM) has been developed to discuss the process required to qualify data generated for the Buried Waste Program (BWP). The data from the BWP tasks conducted at the Radioactive Waste Management Complex (RWMC) and elsewhere will lead to remedial decisions being made which are governed by federal regulations administered by the Environmental Protection Agency (EPA). Data qualification is the process of insuring that only data of planned and known qualities are used to make a decision or answer a question. Although it is the Data Integrity Review Committee's (DIRC) responsibility to insure that the quality of all BWP data is ultimately verified and validated, all personnel who participate in the data gathering process will affect the quality of the data and must be responsible for knowing what is required to produce data of the planned quality. Therefore this manual is addressed to all participants in a data-gathering task. This manual discusses requirements to support data qualification in several areas, including: the sampling and analysis plan; data quality objectives and PARCC goals; sample custody documentation; quality assurance; assembly of the data qualification package; and existing data. 23 refs., 4 figs., 6 tabs

  3. Qualification of quality testing personnel, in particular the training offered

    International Nuclear Information System (INIS)

    Knoedler, D.

    1980-01-01

    Personnel qualification is one of the most important tasks of quality assurance. The qualification is reached by professional education, by experience made on the job and by additional external and company-internal training. A determination of qualification requirements should cover only the general principles. Especially this should be considered specifying the requirements for theoretical knowledge and for examinations since the factor of relevant experience is difficult to be estimated by third parties. Equal principles apply for the personnel of the manufacturer, of the main contractor, of the utility and of the auhtorized inspectors' organizations. The detailed guidelines should be part of the internal QA-systems of the organizations involved. (orig.) [de

  4. 26 CFR 20.6036-2 - Notice of qualification as executor of estate of decedent dying after 1970.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 14 2010-04-01 2010-04-01 false Notice of qualification as executor of estate... AUGUST 16, 1954 Procedure and Administration § 20.6036-2 Notice of qualification as executor of estate of... special notice of qualification as executor of an estate is required to be filed. The requirement of...

  5. Inspection qualification and implementation of ENIQ in Sweden

    International Nuclear Information System (INIS)

    Zettervall, Tommy

    2013-01-01

    Many countries are currently considering their approaches to inspection qualification and risk-informed in-service inspection (RI-ISI) and are carefully assessing experience data. In Europe most of the utilities operating nuclear power plants have joined together to form the European Network for Inspection Qualification ENIQ. In practice, qualification can be performed with varying degrees of complexity and cost, varying from capability statement based on existing evidence, through to an extensive qualification consisting of a detailed Technical Justification (TJ) together with open and blind trials on full-scale test blocks. An Inspection Qualification is an investigation and demonstration, which confirm that an inspection system has the ability to solve its specific tasks. The qualification is a Quality Assurance of an inspection system based on documents and practical trials. A reliable inspection system, based on a reliable qualification and correct prerequisites, will reduce total costs for Licensees and increase the credibility of the inspection result. To get such inspection system, which could be valid for many years, it's of necessity to fulfil all included parts in the process. It begins with the Technical Specification from Licensee, where input data and requirements about the actual component are specified. To get an inspection system that could live over time, the Technical Justification is of importance. Finally the test blocks and used simulation techniques play an important part of the final result, and these test blocks together with TJ form the basis for qualification body's decision. (author)

  6. Commercial Parts Technology Qualification Processes

    Science.gov (United States)

    Cooper, Mark S.

    2013-01-01

    Many high-reliability systems, including space systems, use selected commercial parts (including Plastic Encapsulated Microelectronics or PEMs) for unique functionality, small size, low weight, high mechanical shock resistance, and other factors. Predominantly this usage is subjected to certain 100% tests (typically called screens) and certain destructive tests usually (but not always) performed on the flight lot (typically called qualification tests). Frequently used approaches include those documented in EEE-INST-002 and JPL DocID62212 (which are sometimes modified by the particular aerospace space systems manufacturer). In this study, approaches from these documents and several space systems manufacturers are compared to approaches from a launch systems manufacturer (SpaceX), an implantable medical electronics manufacturer (Medtronics), and a high-reliability transport system process (automotive systems). In the conclusions section, these processes are outlined for all of these cases and presented in tabular form. Then some simple comparisons are made. In this introduction section, the PEM technology qualification process is described, as documented in EEE-INST-002 (written by the Goddard Space Flight Center, GSFC), as well as the somewhat modified approach employed at the Jet Propulsion Laboratory (JPL). Approaches used at several major NASA contractors are also described

  7. 77 FR 52384 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-08-29

    ...-0218] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... from the diabetes mellitus requirement; request for comments. SUMMARY: FMCSA announces receipt of... diabetes mellitus (ITDM) operating commercial motor vehicles (CMVs) in interstate commerce. If granted, the...

  8. 77 FR 65931 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-10-31

    ...-0347] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... diabetes mellitus requirement; request for comments. SUMMARY: FMCSA announces receipt of applications from 12 individuals for exemption from the prohibition against persons with insulin-treated diabetes...

  9. Nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides and industry standards. In addition to the Institute of Electrical and Electronics Engineers (IEEE), the American Society of Mechanical Engineers (ASME) has also undertaken development of its own set of standards for use in qualifying safety-related mechanical equipment. To ensure that the original design and qualification is preserved, engineers need to select and use the correct set of NRC regulations, regulatory guides, industry standards, and generic correspondence. Given that the total number of these documents exceed 200, this task becomes resource intensive. This compilation is the first known publication available to serve the user-community need for a complete and exhaustive single source. Approximately 180 items (Bulletins, Federal Rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides) have been processed separately for inclusion on the data base

  10. Process of establishing design requirements and selecting alternative configurations for conceptual design of a VLA

    Directory of Open Access Journals (Sweden)

    Bo-Young Bae

    2017-04-01

    Full Text Available In this study, a process for establishing design requirements and selecting alternative configurations for the conceptual phase of aircraft design has been proposed. The proposed process uses system-engineering-based requirement-analysis techniques such as objective tree, analytic hierarchy process, and quality function deployment to establish logical and quantitative standards. Moreover, in order to perform a logical selection of alternative aircraft configurations, it uses advanced decision-making methods such as morphological matrix and technique for order preference by similarity to the ideal solution. In addition, a preliminary sizing tool has been developed to check the feasibility of the established performance requirements and to evaluate the flight performance of the selected configurations. The present process has been applied for a two-seater very light aircraft (VLA, resulting in a set of tentative design requirements and two families of VLA configurations: a high-wing configuration and a low-wing configuration. The resulting set of design requirements consists of three categories: customer requirements, certification requirements, and performance requirements. The performance requirements include two mission requirements for the flight range and the endurance by reflecting the customer requirements. The flight performances of the two configuration families were evaluated using the sizing tool developed and the low-wing configuration with conventional tails was selected as the best baseline configuration for the VLA.

  11. Integrated Information System for Higher Education Qualifications

    Directory of Open Access Journals (Sweden)

    Catalin Ionut SILVESTRU

    2012-10-01

    Full Text Available In the present article we aim to study thoroughly and detail aspects related to architectures specific for e-learning and management of human resources training interconnected to management of qualifications. In addition, we take into consideration combining e-learning architectures with software in an e-learning system interconnected with the National Registry of Qualifications of Higher Education, in view of developing and information system that correlates educational supply from higher education from Romania with labor market demands through qualifications. The scientific endeavor consists of original architectural solutions to integrate data, systems, processes, services from various sources and to use them in the proposed system. The practical result of the scientific endeavor is represented by design of architectures required for developing an e-learning system interconnected with the National Registry of Qualifications from Romania, which involve in first stage the qualifications provided by higher education. The proposed innovative solution consists in the fact that the proposed information system combines the advantages of content management system (CMS with learning content management system (LCMS and with reusable learning objects (RLO. Thus, the architecture proposed in the research ensures the integration of a content management system with a portal for information, guidance and support in making a professional project. The integration enables correlation of competences with content areas and specific items from various teaching subjects, thus evaluating the usefulness for this registry from learning/educational perspective. Using the proposed information system in enables correlation among qualifications, content of educational program and continuous self-evaluation opportunities, which facilitate monitoring of progress and adjustment of learning content.

  12. 77 FR 5243 - Proposed Priority, Requirements, Definitions, and Selection Criteria-Arts in Education National...

    Science.gov (United States)

    2012-02-02

    ...-quality arts education and arts integration activities and services in music, dance, theater, media arts... DEPARTMENT OF EDUCATION Proposed Priority, Requirements, Definitions, and Selection Criteria--Arts in Education National Program (AENP) AGENCY: Office of Innovation and Improvement, Department of...

  13. Instructor qualification for radiation safety training at a national laboratory

    International Nuclear Information System (INIS)

    Trinoskey, P.A.

    1994-10-01

    Prior to 1993, Health Physics Training (HPT) was conducted by the Lawrence Livermore National Laboratory (LLNL) health physics group. The job requirements specified a Masters Degree and experience. In fact, the majority of Health Physicists in the group were certified by the American Board of Health Physics. Under those circumstances, it was assumed that individuals in the group were technically qualified and the HPT instructor qualification stated that. In late 1993, the Health Physics Group at the LLNL was restructured and the training function was assigned to the training group. Additional requirements for training were mandated by the Department of Energy (DOE), which would necessitate increasing the existing training staff. With the need to hire, and the policy of reassignment of employees during downsizing, it was imperative that formal qualification standards be developed for technical knowledge. Qualification standards were in place for instructional capability. In drafting the new training qualifications for instructors, the requirements of a Certified Health Physicists had to be modified due to supply and demand. Additionally, for many of the performance-based training courses, registration by the National Registry of Radiation Protection Technologists is more desirable. Flexibility in qualification requirements has been incorporated to meet the reality of ongoing training and the compensation for desirable skills of individuals who may not meet all the criteria. The qualification requirements for an instructor rely on entry-level requirements and emphasis on goals (preferred) and continuing development of technical and instructional capabilities

  14. Inspection procedure and essential parameters in NDT qualification

    International Nuclear Information System (INIS)

    Sarkimo, M.

    2000-06-01

    The objective of the inspection qualification is to ensure that applied non-destructive methods (NDT) have the required performance. The approach of the qualification process is systematic and carefully documented and therefore some new requirements can be seen concerning the composition of the documentation. There are also new document types, that only application of the inspection qualification requires. The most important of these is the technical justification, that includes the documented evidences concerning the performance of the inspection system. This publication includes two reports: 'Compilation of the inspection procedure' and 'Essential/influential parameters in NDT qualification'. The former of these discusses the issues to be considered in an inspection procedure especially from the point of view of the mechanised ultrasonic testing. The later report explains the parameters formulated to analyse in the technical justification all aspects of the inspection application. (orig.)

  15. Application of operating experience in environmental qualification program

    International Nuclear Information System (INIS)

    Lee, S.Y.; Wise, R.

    2000-01-01

    Environmental qualification (EQ) of equipment related to nuclear safety has been carried out in the nuclear community since the 70's. It started with electrical equipment and then expanded to include mechanical equipment. During this evolutionary process, the methods used for EQ have gone through a long period of refinement and clarification. Prior to 1971, qualification for equipment in licensed nuclear power plants was based on the use of electrical components of commonly accepted high industrial quality without the benefit of specific environmental qualification standards. Between 1971 and 1974, most plants used the criteria of IEEE Standard 323-1971 as the basis for demonstrating qualification. Also during this period related 'daughter' standards, mainly by IEEE, became available which addressed qualification for specific equipment items. After July 1974, plants were required to meet the more comprehensive guidelines specified in IEEE Standard 323-1974 and the related 'daughter' standards. IEEE Standard 323-1974 later evolved into IEEE Standard 323-1983. For nuclear power plants built in Ontario during the 70's, i.e. Pickering B and Bruce B, has included the environmental qualification requirements in their respective nuclear safety design guides. It is now recognized that they are not up to the current EQ standards. Darlington, constructed during the 80's, implemented the environmental qualification program in its project. An Environmental Qualification (EQ) Program is now under way in Ontario Power Generation (OPG) to formally implement the Environmental Qualification for Bruce B, Pickering B, and Pickering A and to preserve the Qualification for Darlington G.S. This paper makes a thorough a review of the standard methods used in the past by utilities for environmental qualification. These methods include type testing, analysis, and operating experience. Both type testing and analysis have been clearly defined in standards listed in References [2] to [6] and

  16. Reaction Qualifications Revisited

    DEFF Research Database (Denmark)

    Lippert-Rasmussen, Kasper

    2009-01-01

    to a person's effectiveness by causing a favourable reaction in customers, co-workers etc. (for short: recipients) - are involved, this assumption is false. Building on work by Wertheimer, Mason, and Miller, this paper proposes an account of the reaction qualifications that count, from the point of view...... preferences, recipients should not respond to the applicant actually hired on the basis of their (the recipients') racial preferences. My account decomposes the meritocratic ideal into four separate norms, one of which applies to recipients rather than to selectors. Finally, it defends the view that reaction...... qualifications based on antimeritocratic reactions, while not unproblematic, are not entirely irrelevant from the point of view of merit. Notably, selectors need not discount them when no one - including the targets of the objectionable preferences - is unfairly disadvantaged. Because not all problematic...

  17. An integrated approach for requirement selection and scheduling in software release planning

    NARCIS (Netherlands)

    Li, C.; van den Akker, Marjan; Brinkkemper, Sjaak; Diepen, Guido

    2010-01-01

    It is essential for product software companies to decide which requirements should be included in the next release and to make an appropriate time plan of the development project. Compared to the extensive research done on requirement selection, very little research has been performed on time

  18. Qualification of conditioning process

    International Nuclear Information System (INIS)

    Wolf, J.

    1989-01-01

    A conditioning process is qualified by the PTB if the execution of pre-treatment and conditioning occurs so that a safe and orderly final storage of the products and waste containers produced can be assumed. All the relevant operating conditions for the plant are laid down by the producer/conditioner of the waste in a handbook. The elements of product inspection by process qualification are shown in tabular form. (DG) [de

  19. Uber die Vereinbarkeit individueller Bildungsbedurfnisse und betrieblicher Qualifikationsanforderungen (On the Compatibility of Individual Needs for Education and Employment-Related Qualification Requirements).

    Science.gov (United States)

    Heid, Helmut

    1999-01-01

    States that a tendency has developed to orientate educational-practical acting using learners' educational needs, while representatives of the employment system deduce political and practical educational maxims from requirements that result from economic structural changes. Defines the instructional importance of individual educational needs and…

  20. REGULATION OF NATIONAL QUALIFICATIONS SYSTEMS

    Directory of Open Access Journals (Sweden)

    Anna A. Muravyeva

    2014-01-01

    Full Text Available The paper looks into the diverse aspects of qualifications system regulation, designed for balancing the supply and demand in the labor and educational service markets. Both the objects and mechanisms of such regulation are described. Special attention is given to institutions, involved in regulation of qualifications, and their jurisdiction. Another emphasis is on the industry-related regulation of qualifications which proved to be effective both on the national and European level. Such structures were first established on the national levels to regulate the qualifications and ensure their comparability and compatibility, given the economic globalization and growing labor and academic mobility. The author points out the role of the ministries of education and labor in maintaining a steady qualifications system, and outlines the positive experience of Great Britain using the industry councils for continuing development of qualifications system.

  1. Qualification of NDT systems for in-service inspections of nuclear power plant pressure vessels; Ydinvoimalaitosten paineastioiden maeaeraeaikaistarkastuksissa kaeytettaevien NDT-jaerjestelmien paetevoeinti

    Energy Technology Data Exchange (ETDEWEB)

    Elfving, K

    1998-11-01

    The goal of this study is to determine the requirements of the in-service inspection qualification in Europe, their feasibility in practice and to find out possible manufacture defects in test pieces used in practical trials. The literature study consists of qualification requirements set by European regulatory bodies and by the European nuclear power utilities. Also a brief summary of qualification requirements set by ASME Code, Section XI and comparison between ASME and European qualification requirements is included 24 refs.

  2. Regulatory requirements for nuclear power plant site selection in Malaysia-a review.

    Science.gov (United States)

    Basri, N A; Hashim, S; Ramli, A T; Bradley, D A; Hamzah, K

    2016-12-01

    Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

  3. IDENTIFYING OPERATIONAL REQUIREMENTS TO SELECT SUITABLE DECISION MODELS FOR A PUBLIC SECTOR EPROCUREMENT DECISION SUPPORT SYSTEM

    Directory of Open Access Journals (Sweden)

    Mohamed Adil

    2014-10-01

    Full Text Available Public sector procurement should be a transparent and fair process. Strict legal requirements are enforced on public sector procurement to make it a standardised process. To make fair decisions on selecting suppliers, a practical method which adheres to legal requirements is important. The research that is the base for this paper aimed at identifying a suitable Multi-Criteria Decision Analysis (MCDA method for the specific legal and functional needs of the Maldivian Public Sector. To identify such operational requirements, a set of focus group interviews were conducted in the Maldives with public officials responsible for procurement decision making. Based on the operational requirements identified through focus groups, criteria-based evaluation is done on published MCDA methods to identify the suitable methods for e-procurement decision making. This paper describes the identification of the operational requirements and the results of the evaluation to select suitable decision models for the Maldivian context.

  4. Framework of orientation for the discussion of measures required to maintain and further the expert knowledge and qualification of nuclear power plant managers and supervisors

    International Nuclear Information System (INIS)

    Farber, G.

    1984-01-01

    This report is focussed on the important aspects of the training and retraining of nuclear power plant managers and supervisors. The functional levels of the onsite operating organization of nine nuclear power plants are described and analyzed in order to determine the comparability of management positions as well as the responsibilities of the job incumbents. Retraining requirements are suggested depending on position, responsibilities, and relevance to safety. The manager's role in case of emergencies leads to specific demands with regard to regular training to cope with inadequate core cooling and to mitigate accidents. (orig.) [de

  5. Technical evaluation of seismic qualification of safety-related equipment

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Yang Hui; Park, Heong Gee; Park, Yeong Seok [Univ. of Incheon, Incheon (Korea, Republic of)

    1994-04-15

    This study is purposed to evaluate the technical acceptability of the procedures and techniques of seismic qualifications which were performed for the YGN 3 and 4 safety-related equipment.This study is also targeted to suggest a systematized technical procedure guide for the effective performance and review of the seismic qualification, which reflects the most up-to-date licensing requirements and state-of the-art.

  6. Impact of the draft DOE Training and Qualification Standard on an established training and qualification program

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1999-01-01

    One of the provisions of Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2 was that the US Department of Energy (DOE) hor e llipsis Develop and institute ahor e llipsiscourse in criticality and criticality safety hor e llipsis to serve as the foundation for a program of formal qualification of criticality engineers. In response, a draft DOE standard establishing requirements for a formal qualification program for nuclear criticality safety (NCS) engineers has been prepared and is currently in review. The Oak Ridge Y-12 plant implemented a formal training and qualification program for NCS engineers in 1995. The program complies with existing DOE requirements. The program was developed using a performance-based systematic approach to training and is accomplished through structured mentoring where experienced personnel interact with candidates through various learning exercises. Self-study, exercises, and work under instruction are all utilized. The candidate's performance is evaluated by mentors and oral boards. Competency gained through experience at other sites can also be credited. Technical portions of the program are primarily contained in an initial Engineer-in-Training segment and in subsequent task-specific qualifications. The Engineer-in-Training segment exposes the candidate to fundamental NCS concepts through example problems; ensures the initial compliance training requirements are met; and includes readings from applicable procedures, technical documents, and standards. Upon completion of this initial training, candidates proceed to task qualifications. Tasks are defined NCS activities such as operational reviews, criticality safety evaluations, criticality safety computations, criticality accident alarm system (CAAS) evaluations, support for emergency management, etc. Qualification on a task basis serves to break up training into manageable pieces and expedites qualification of candidates to perform specific production activities. The

  7. Qualification tests for shift personnel in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Fechner, J B [Bundesministerium des Innern, Bonn (Germany, F.R.)

    1978-02-01

    The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors.

  8. Qualification tests for shift personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Fechner, J.B.

    1978-01-01

    The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors. (orig.) [de

  9. Development of the material selection practice - a study exploring articulation of material requirements

    DEFF Research Database (Denmark)

    Lenau, Torben Anker; Hasling, Karen Marie

    2014-01-01

    indicates that students focus on technical requirements when using the matrix and justifying their selection of materials. This is surprising since the students attend an arts and crafts oriented design school and are encouraged and guided to consider non-technical requirements, as part of the course where...... the matrix is introduced. A possible reason for the undesired behavior could be that students are allowed very freely to define their own matrices, having only little guidance to which requirements to use. A more formal procedure for making the material matrices is therefore proposed. The procedure requires...

  10. AGR-2 Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Michael L. Abbott

    2010-09-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  11. AGR-2 Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Abbott, Michael L.

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  12. Qualification of contractor/consultant instructors

    International Nuclear Information System (INIS)

    Hanson, H.D.

    1985-01-01

    Following a brief discussion of the role of consultant instructors in Public Service Electric and Gas Company's training organization, the qualification process is presented. Consultant instructors are provided with information regarding supervision of the trainees and the instructional process and procedures required. Each individual must have his or her instructional capability, supervisory skills and technical competence verified and documented prior to conducting training independently. Concluding comments describe the overall satisfactory experience with this program

  13. Requirements to be taken into account in the design, qualification startup and operation of electrical equipment for safety-related electrical systems

    International Nuclear Information System (INIS)

    1985-07-01

    RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to provide the rules to be respected in order that safety-related electrical systems can perform its function under plausible operating conditions

  14. Data Qualification guidelines

    International Nuclear Information System (INIS)

    Edwards, T.B.; Shine, E.P.

    1992-01-01

    Data Qualification (DQ) is a formal, technical process whose objective is to affirm that experimental data are suitable for their intended use. Although it is not possible to develop a fixed recipe for the DQ process to cover all test situations, these general guidelines have been developed for the Nuclear Engineering Section to establish a framework for qualifying data from steady-state processing. These guidelines outline the role of the DQ team providing insight into the planning and conducting of the DQ process

  15. Process qualification and testing of LENS deposited AY1E0125 D-bottle brackets

    International Nuclear Information System (INIS)

    Atwood, Clinton J.; Smugeresky, John E.; Jew, Michael; Gill, David Dennis; Scheffel, Simon

    2006-01-01

    The LENS Qualification team had the goal of performing a process qualification for the Laser Engineered Net Shaping(trademark)(LENS(reg s ign)) process. Process Qualification requires that a part be selected for process demonstration. The AY1E0125 D-Bottle Bracket from the W80-3 was selected for this work. The repeatability of the LENS process was baselined to determine process parameters. Six D-Bottle brackets were deposited using LENS, machined to final dimensions, and tested in comparison to conventionally processed brackets. The tests, taken from ES1E0003, included a mass analysis and structural dynamic testing including free-free and assembly-level modal tests, and Haversine shock tests. The LENS brackets performed with very similar characteristics to the conventionally processed brackets. Based on the results of the testing, it was concluded that the performance of the brackets made them eligible for parallel path testing in subsystem level tests. The testing results and process rigor qualified the LENS process as detailed in EER200638525A

  16. Results of a literature review on the environmental qualification of low-voltage electric cables

    International Nuclear Information System (INIS)

    Lofaro, R.; Lee, B.; Villaran, M.; Gleason, J.; Aggarwal, S.

    1995-01-01

    In the design of nuclear power plants in the US, safety-related electric equipment must be qualified to provide reasonable assurance it can withstand the effects of a design basis event (DBE) and still be able to perform its prescribed safety function, even if the accident were to occur at the end of its service life. The requirement for environmental qualification (EQ) originates from the General Design Criteria in the Code of Federal Regulations, Title 10, Part 50 (10 CFR 50). The acceptable method of performing the qualification of this equipment has evolved over the years, starting with the NRC Division of Operating Reactors (DOR) Guidelines, which were issued in Bulletin 79--01B, and NUREG-0588 requirements and ending with the current EQ Rule, 10 CFR 50.49. While the EQ methods described in these documents have the same overall objective, there are some notable differences for which a clear technical basis has not been established. One difference is the preaging requirement for equipment prior to LOCA testing. In addition, specific issues related to current EQ practices have been raised by the US NRC which need to be addressed. These issues, which are discussed in detail later in this paper, are related to the sources of conservatism and uncertainty in IEEE Standard 323--1974, which is the qualification standard currently endorsed by the NRC. To address these issues, the NRC Office of Nuclear Reactor Regulation (NRR) implemented a Task Action Plan (TAP), and the Office of Nuclear Reactor Research (RES) initiated a complementary research program. The current focus of this program is on the qualification of low-voltage instrumentation and control cables. These cables were selected since they are not typically replaced on a routine basis, and their degradation could impact plant safety

  17. Decree of the Czechoslovak Atomic Energy Commission No. 191/1989 on procedures, terms and conditions for examining special professional qualification and competence of selected nuclear facility personnel

    International Nuclear Information System (INIS)

    1995-01-01

    The procedures, terms and conditions for examining special professional competence of selected nuclear facility personnel are specified, including conditions for professional training and for issuing licenses qualifying the personnel for their work. Nuclear safety-related jobs at nuclear facilities are listed. Professional licenses with a two-year term of validity are granted by the Czechoslovak Atomic Energy Agency (CSAEC) to candidates who have passed examination before the State Examination Commission. Personnel training may only be performed by bodies authorized for that by the CSAEC. The Decree entered into force on 1 January 1990. (J.B.)

  18. Nuclear power reactor security personnel training and qualification plan reviewer workbook

    International Nuclear Information System (INIS)

    1979-06-01

    The Training and Qualification Plan Reviewer Workbook has been developed to provide the information required for evaluating the adequacy of the Training and Qualification (T and Q) Plans developed to meet the requirements of 10 CFR 73.55(b)(4) and 10 CFR 73, Appendix B

  19. 78 FR 12955 - Final Requirements, Definitions, and Selection Criteria-Native American Career and Technical...

    Science.gov (United States)

    2013-02-26

    ... career and technical education programs (20 U.S.C. 2326(e)). This notice does not preclude us from... DEPARTMENT OF EDUCATION 34 CFR Chapter IV [Docket ID ED-2012-OVAE-0053] Final Requirements, Definitions, and Selection Criteria--Native American Career and Technical Education Program (NACTEP) [Catalog...

  20. Determining the requirements for e-selection in a small recruitment company - using the regulative cycle

    NARCIS (Netherlands)

    Bondarouk, Tatiana; Ruel, Hubertus Johannes Maria; Timmermans, P.; Buragga, K.A.; Zaman, N.

    2013-01-01

    The requirements for e-selection technology to be of practical use for Company T have been investigated. Company T’s main business is in identifying and seconding personnel, especially in the technical sector, and it had been anticipating a shortage in the supply of candidates. This served as the

  1. Qualification of uranium-molybdenum alloy fuel - conclusions of an international workshop

    International Nuclear Information System (INIS)

    Snelgrove, J.L.; Languille, A.

    2000-01-01

    Thirty-one participants representing 21 reactors, fuel developers, fuel fabricators, and fuel reprocessors in 11 countries discussed the requirements for qualification of U-Mo alloy fuel at a workshop held at Argonne National Laboratory on January 17-18, 2000. Consensus was reached that the qualification plans of the U.S. RERTR program and the French U-Mo fuel development program are valid. The items to be addressed during qualification are summarized in the paper. (author)

  2. The implementing of the training, examination and qualification for QA auditor

    International Nuclear Information System (INIS)

    Ma Xiaozheng; Han Peicong; Zhang Zhongyuan; Zhu Guoliang

    2007-01-01

    China Power Investment Corporation has implemented the training, examination and qualification for QA auditor based on the related requirements of the nuclear safety documents. The bases, planning of the procedure, implementing procedure and suggestions for implementing the training, examination and qualification are described in this article. That can be used as the reference for implementing the training, examination and qualification for QA auditor, as well as for establishment of the related guide. (authors)

  3. Qualification of RETRAN for simulator applications

    International Nuclear Information System (INIS)

    Harrison, J.F.

    1988-01-01

    The use of full-scope control room replica simulators increased substantially following the accident at Three Mile Island Unit 2. The technical capability required to represent severe events has been included, in varying degrees, in most simulators purchased since the TMI-2 accident. The ability of the instructor to create a large variety of combinations of malfunctions has also greatly expanded. The nuclear industry has developed a standard which establishes the minimum functional requirements for full-scope nuclear control room simulators used for operator training. This standard, ANSI/ANS-3.5, was first issued in 1981 and was reissued in 1985. A method for performing simulator qualification with best estimate analytical data has been proposed in EPRI NP-4243, Analytic Simulator Qualification Methodology. The idea presented there is to choose a set of transients which drive the simulator into all the system conditions (dynamic states) likely to be encountered during operator training. The key observable parameters for each state are compared to analyses performed with the best estimate analytical model The closeness of the comparison determines the fidelity of the simulator. The approach described in EPRI NP-4243 has been adapted for evaluating RETRAN's capability for use in simulator qualification. RETRAN analyses which compare the RETRAN results to plant or test facility data are evaluated with respect to the simulator test matrix documented in EPRI NP-4243

  4. Environmental qualification program for Wolsong project

    International Nuclear Information System (INIS)

    Duggal, A.; Johal, H.; Yee, F.; Suh, S.K.

    1995-01-01

    The Wolsong EQ Program is a process that begins at the design concept stage and continues throughout the operating life of the station. As all components may not have a 30 year service life without periodic maintenance, the EQ Program becomes an important management tool for the owner of the plant. First, the environmental conditions are predicted for the postulated events. Next, suitably qualified equipment is specified and procured. Then the equipment is installed according to specific instructions. Finally, by means of ongoing maintenance and replacement of parts, the qualification of the equipment is maintained during the operating life of the plant. Proper documentation and traceability is required at all stages of the program. As defined in the Wolsong Project Environmental Qualification Design Guide a comprehensive Environmental Qualification (EQ) Program ensures that safety related equipment located in an area in which a harsh environment could occur, can function when required for the life of the station . This program was implemented at the beginning of the Wolsong project. Using this program, components/equipment are qualified prior to installation and a maintenance program is established to keep equipment 'qualified' throughout the station life

  5. SRNL PHASE 1 Assessment Of The WTP Waste Qualification Program

    International Nuclear Information System (INIS)

    Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

    2012-01-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the

  6. 23 CFR 1350.4 - Qualification requirements.

    Science.gov (United States)

    2010-04-01

    ....g., law, regulation, binding policy directive, letter from the Governor) identifying the designated... the presence of motorcyclists on or near roadways and safe driving practices that avoid injuries to... specific countermeasures to reduce impaired motorcycle operation with strategies designed to reach...

  7. 77 FR 6676 - Office of Inspector General; Contractor Requirements

    Science.gov (United States)

    2012-02-09

    ... POSTAL SERVICE 39 CFR Part 230 Office of Inspector General; Contractor Requirements AGENCY: Postal... for contractors employed by the Office of Inspector General. The rule also emphasizes consistency in contractor selection, and clarifies the OIG's exclusive authority to set qualifications and standards for its...

  8. Environmental data qualification system

    International Nuclear Information System (INIS)

    Hester, O.V.; Groh, M.R.

    1989-01-01

    The Integrated Environmental Data Management System (IEDMS) is a PC-based system that can support environmental investigations from their design stage and throughout the duration of the study. The system integrates data originating from the Sampling and Analysis Plan, field data and analytical findings. The IEDMS automated features include sampling guidance forms, barcoded sample labels and tags, field and analytical forms reproduction, sample tracking, analytical data qualification, completeness reports, and results and QC data reporting. The IEDMS has extensive automated capabilities that support a systematic and comprehensive process for performing quality assessment of EPA-CLP chemical analyses data. One product of this process is a unique and extremely useful tabular presentation of the data. One table contains the complete set of results and QC data included on the CLP data forms while presenting the information consistent with the chronology in which the analysis was performed. 3 refs., 1 fig

  9. Ageing management and equipment qualification

    International Nuclear Information System (INIS)

    Stahl, Gunnar

    2014-01-01

    The knowledge of how the environment and load of organic material in general and especially polymers and lubricants, is affecting the degradation of important properties, have increased during the last decade. However the restrictions using established additives like some color pigments due to their poisonousness e.g. pigments based at cadmium, lead, mercury etc. have caused problems when replacing additives to polymers. The replacement additives have often been used in new design without going through the required material qualification procedure. There have also been observed that some non-qualified and non-approved materials have been installed in some power plants due to false documentation. There are also a lot of new manufacturers, of materials similar to the previously qualified materials, active at the market. This increases the difficulty to ensure that the required material quality is used. New materials, new additives and new manufacturers makes if more and more difficult to assure that the expected material is present. This causes more strict demands of how the new materials often used in equipment at type-testing and in replacement materials are analyzed and documented. By implementing new steps for chemical, mechanical and electrical analysis and increase the general quality assurance content this issue can be managed. (authors)

  10. Philosophies Applied in the Selection of Space Suit Joint Range of Motion Requirements

    Science.gov (United States)

    Aitchison, Lindsway; Ross, Amy; Matty, Jennifer

    2009-01-01

    Space suits are the most important tool for astronauts working in harsh space and planetary environments; suits keep crewmembers alive and allow them to perform exploration, construction, and scientific tasks on a routine basis over a period of several months. The efficiency with which the tasks are performed is largely dictated by the mobility features of the space suit. For previous space suit development programs, the mobility requirements were written as pure functional mobility requirements that did not separate joint ranges of motion from the joint torques. The Constellation Space Suit Element has the goal to make more quantitative mobility requirements that focused on the individual components of mobility to enable future suit designers to build and test systems more effectively. This paper details the test planning and selection process for the Constellation space suit pressure garment range of motion requirements.

  11. Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6?

    International Nuclear Information System (INIS)

    P.L. Cloke

    2000-09-01

    The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities

  12. Comparative analysis of quality assurance requirements for selected LMFBR components of classes 1, 2 and 3

    International Nuclear Information System (INIS)

    Kleinert, K.P.

    1992-01-01

    The study analyses and compares German, French, British and Italian practices and procedures applied for various LMFBR projects both related to the quality assurance system and related to the particular type of class of component:Class 1: primary reactor vessel; Class 2: Secondary sodium pump; Class 3: Primary cold trap. Various areas of analysis and comparison were selected to identify the underlying concepts of grading of requirements and measures, to identify the similarities and differences, and to give recommendations for further actions concerning quality assurance requirements 60 refs., 21 tabs., 6 figs

  13. The french safety approach regarding equipment qualification

    International Nuclear Information System (INIS)

    Jalouneix, J.; Deletre, G.; Henry, J.Y.; Rousseau, L.

    1989-10-01

    The qualification of the equipment, used in France on nuclear reactors and reactor components, is discussed. The approach on safety involves the qualification of mechanical and electrical components, under operating and under seismic conditions. The principles of the qualification program and the list of the equipment concerned, are given. The conditions in which qualification tests are performed and the methods applied, are summarized. The actions for preserving the qualification procedures, are considered

  14. Development and qualification of materials and processes for radiation shielding of Galileo spacecraft electronic components

    International Nuclear Information System (INIS)

    Hribar, F.; Bauer, J.L.; O'Donnell, T.P.

    1990-01-01

    Several materials and processing methods were evaluated for use on the JPL Galileo spacecraft in the area of radiation shielding for electronics. Development and qualification activities involving an aluminum structural laminate are described. These activities included requirements assessment, design tradeoffs, materials selection, adhesive bonding development, mechanical properties measurements, thermal stability assessment, and nondestructive evaluation. This paper presents evaluation of three adhesives for bonding tantalum to aluminum. The concept of combining a thin sheet of tantalum with two outer aluminum face sheets using adhesive bonding was developed successfully. This radiation shield laminate also provides a structural shear plate for mounting electronic assemblies

  15. cis and trans requirements for the selective packaging of adenovirus type 5 DNA.

    OpenAIRE

    Gräble, M; Hearing, P

    1992-01-01

    Polar packaging of adenovirus DNA into virions is dependent on the presence of cis-acting sequences at the left end of the viral genome. Our previous analyses demonstrated that the adenovirus type 5 (Ad5) packaging domain (nucleotides 194 to 358) is composed of at least five elements that are functionally redundant. A repeated sequence, termed the A repeat, was associated with packaging function. Here we report a more detailed analysis of the requirements for the selective packaging of Ad5 DN...

  16. Progress on EPRI electrical equipment qualification research

    International Nuclear Information System (INIS)

    Sliter, G.E.

    1983-01-01

    The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

  17. Selection of the battery pack parameters for an electric vehicle based on performance requirements

    Science.gov (United States)

    Koniak, M.; Czerepicki, A.

    2017-06-01

    Each type of vehicle has specific power requirements. Some require a rapid charging, other make long distances between charges, but a common feature is the longest battery life time. Additionally, the battery is influenced by factors such as temperature, depth of discharge and the operation current. The article contain the parameters of chemical cells that should be taken into account during the design of the battery for a specific application. This is particularly important because the batteries are not properly matched and can wear prematurely and cause an additional costs. The method of selecting the correct cell type should take previously discussed features and operating characteristics of the vehicle into account. The authors present methods of obtaining such characteristics along with their assessment and examples. Also there has been described an example of the battery parameters selection based on design assumptions of the vehicle and the expected performance characteristics. Selecting proper battery operating parameters is important due to its impact on the economic result of investments in electric vehicles. For example, for some Li-Ion technologies, the earlier worn out of batteries in a fleet of cruise boats or buses having estimated lifetime of 10 years is not acceptable, because this will cause substantial financial losses for the owner of the rolling stock. The presented method of choosing the right cell technology in the selected application, can be the basis for making the decision on future battery technical parameters.

  18. 75 FR 60862 - Qualification of Drivers; Exemption Renewals; Vision

    Science.gov (United States)

    2010-10-01

    ...-2006-24015; FMCA- 2008-0106; FMCSA-2008-0174] Qualification of Drivers; Exemption Renewals; Vision.... SUMMARY: FMCSA previously announced its decision to renew the exemptions from the vision requirement in... exempt individuals from the vision requirement if the exemptions granted will not compromise safety. The...

  19. 78 FR 1919 - Qualification of Drivers; Exemption Applications; Vision

    Science.gov (United States)

    2013-01-09

    ...-0339] Qualification of Drivers; Exemption Applications; Vision AGENCY: Federal Motor Carrier Safety... announces receipt of applications from 14 individuals for exemption from the vision requirement in the Federal Motor Carrier Safety Regulations. They are unable to meet the vision requirement in one eye for...

  20. 46 CFR 2.75-70 - Welding procedure and performance qualifications.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Welding procedure and performance qualifications. 2.75... for Construction Personnel § 2.75-70 Welding procedure and performance qualifications. (a) Welding... requirements for the welding of pressure piping, boilers, pressure vessels, and nonpressure vessel type tanks...

  1. 10 CFR 50.120 - Training and qualification of nuclear power plant personnel.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Training and qualification of nuclear power plant... Training and qualification of nuclear power plant personnel. (a) Applicability. The requirements of this... each holder of a combined license issued under part 52 of this chapter for a nuclear power plant of the...

  2. Methodology for LOCA analysis and its qualification procedures for PWR reload licensing

    International Nuclear Information System (INIS)

    Serrano, M.A.B.

    1986-01-01

    The methodology for LOCA analysis developed by FURNAS and its qualification procedure for PWR reload licensing are presented. Digital computer codes developed by NRC and published collectively as the WREM package were modified to get versions that comply to each requirement of Brazilian Licensing Criteria. This metodology is applied to Angra-1 basic case to conclude the qualification process. (Author) [pt

  3. A hierarchical modeling methodology for the definition and selection of requirements

    Science.gov (United States)

    Dufresne, Stephane

    This dissertation describes the development of a requirements analysis methodology that takes into account the concept of operations and the hierarchical decomposition of aerospace systems. At the core of the methodology, the Analytic Network Process (ANP) is used to ensure the traceability between the qualitative and quantitative information present in the hierarchical model. The proposed methodology is implemented to the requirements definition of a hurricane tracker Unmanned Aerial Vehicle. Three research objectives are identified in this work; (1) improve the requirements mapping process by matching the stakeholder expectations with the concept of operations, systems and available resources; (2) reduce the epistemic uncertainty surrounding the requirements and requirements mapping; and (3) improve the requirements down-selection process by taking into account the level of importance of the criteria and the available resources. Several challenges are associated with the identification and definition of requirements. The complexity of the system implies that a large number of requirements are needed to define the systems. These requirements are defined early in the conceptual design, where the level of knowledge is relatively low and the level of uncertainty is large. The proposed methodology intends to increase the level of knowledge and reduce the level of uncertainty by guiding the design team through a structured process. To address these challenges, a new methodology is created to flow-down the requirements from the stakeholder expectations to the systems alternatives. A taxonomy of requirements is created to classify the information gathered during the problem definition. Subsequently, the operational and systems functions and measures of effectiveness are integrated to a hierarchical model to allow the traceability of the information. Monte Carlo methods are used to evaluate the variations of the hierarchical model elements and consequently reduce the

  4. Large Bore Powder Gun Qualification (U)

    Energy Technology Data Exchange (ETDEWEB)

    Rabern, Donald A. [Los Alamos National Laboratory; Valdiviez, Robert [Los Alamos National Laboratory

    2012-04-02

    A Large Bore Powder Gun (LBPG) is being designed to enable experimentalists to characterize material behavior outside the capabilities of the NNSS JASPER and LANL TA-55 PF-4 guns. The combination of these three guns will create a capability to conduct impact experiments over a wide range of pressures and shock profiles. The Large Bore Powder Gun will be fielded at the Nevada National Security Site (NNSS) U1a Complex. The Complex is nearly 1000 ft below ground with dedicated drifts for testing, instrumentation, and post-shot entombment. To ensure the reliability, safety, and performance of the LBPG, a qualification plan has been established and documented here. Requirements for the LBPG have been established and documented in WE-14-TR-0065 U A, Large Bore Powder Gun Customer Requirements. The document includes the requirements for the physics experiments, the gun and confinement systems, and operations at NNSS. A detailed description of the requirements is established in that document and is referred to and quoted throughout this document. Two Gun and Confinement Systems will be fielded. The Prototype Gun will be used primarily to characterize the gun and confinement performance and be the primary platform for qualification actions. This gun will also be used to investigate and qualify target and diagnostic modifications through the life of the program (U1a.104 Drift). An identical gun, the Physics Gun, will be fielded for confirmatory and Pu experiments (U1a.102D Drift). Both guns will be qualified for operation. The Gun and Confinement System design will be qualified through analysis, inspection, and testing using the Prototype Gun for the majority of process. The Physics Gun will be qualified through inspection and a limited number of qualification tests to ensure performance and behavior equivalent to the Prototype gun. Figure 1.1 shows the partial configuration of U1a and the locations of the Prototype and Physics Gun/Confinement Systems.

  5. A qualitative inquiry of educational requirements of selected professions in the Oklahoma aerospace industry

    Science.gov (United States)

    Walker, Casey Jerry Kennon

    Interview of incumbents of intellectual capital positions at Boeing. The aerospace industry is a dynamic industry that requires continual skill updates to keep up with advancements in technology and operational trends within the industry. The purpose of this study was to examine intellectual capital requirements of selected professional positions within the Boeing Company in Oklahoma. Data obtained through interviews was used to determine if educational skills gaps existed. The findings of the study can be used to develop an aerospace educational pipeline based on collaborative relationships between industry and higher education to facilitate educational and training programs. Three broad research questions were used to address and support the findings of this study related to educational background, career progression, and gaps. A purposive sample of 10 professional positions was selected for interview using an interview guide containing 18 questions. Data was analyzed using manual coding techniques. Findings and conclusions. The study found that minimum education requirements for selected professional positions consisted of a bachelor's degree. Although the majority of participants identified a business degree as optimal, several participants indicated that an education background from multiple disciplines would provide the greatest benefit. Data from interviews showed educational degrees were not specialized enough and skills required to perform job functions were obtained through direct on the job experience or through corporate training. Indications from participant responses showed employees with a thorough knowledge of government acronyms had a decided advantage over those that did not. Recommendations included: expanding the study to multiple organizations by conducting a survey; expanding industry and academic partnerships; establishing a structured educational pipeline to fill critical positions; creating broad aerospace curricula degree programs tailored

  6. Development and Qualification of ATV Propulsion Assemblies

    Science.gov (United States)

    Riehle, M.; Jost, R.

    2002-01-01

    In the frame of the development and operation of the International Space Station ISS, the European Space Agency ESA is not only contributing experiments and a laboratory module but also logistics capacity. This purpose of supplying the ISS shall be covered by an unmanned, Automated Transfer Vehicle (ATV) that will be launched for the first time in 2004 by Ariane 5. The development of the ATV is in close conjunction to the future Ariane 5 launch capacity of about 20 tons injected into low earth orbit. Thus this unmanned transporter will be a quite large space craft that is subjected to fulfil several mission objectives apart of only delivering cargo such as multiple automatic docking/de-docking, re-boost services and re-fuelling. For those reasons and due to its dimensions the propulsion sub-system is one of the most sophisticated in the field of space propulsion. Even safety issues of manned space flight have to be applied since the pressurised cargo section is part of the ISS when docked to the manned modules. This leads to by far the largest but also the most sophisticated propulsion system ever built in Europe. Astrium as one of the major partners of this european project is responsible for this major system that will be described in the paper. Focusing on the major core assemblies such as multi thruster platforms, pressure control system incl. safety and redundancy mechanisms as well as tanks and other components that completes a propulsion system. System Design and Qualification Starting from the basic criteria the paper will present the major performance requirements such as pressures, thrust levels and other parameters that led to the selection of major components of the system such as thrusters, valves, tanks, etc. Some of the component could be selected from off the shelve, whereas other core components such as the 200N Attitude Control and Braking Thrusters or Propellant Tanks had to be newly developed. The stepwise approach of development and careful

  7. Experience on environmental qualification of safety-related components for Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Yu, A.S.; Kukreti, B.M.

    1987-01-01

    The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station

  8. The IB Diploma and UK University Degree Qualifications

    Science.gov (United States)

    Frank-Gemmill, Gerda

    2013-01-01

    In recent years the International Baccalaureate (IB) Diploma has become widely accepted as a university-entry qualification in the UK, but there has been little quantitative research into the achievements of IB students at degree level. This study investigates IB students from one selective independent school who entered UK universities between…

  9. Establishment of functional requirements to DC-connected wind turbine and their use in concept selection

    DEFF Research Database (Denmark)

    Dincan, Catalin Gabriel; Kjær, Philip Carne; Chen, Yu-Hsing

    2017-01-01

    , but they are all still at an immature technology level, as no substantial experience from full-scale detailed design exists. By employing a functional failure mode and effects analysis (F-FMEA) with a decision making tool (Pugh Matrix), the paper presents a structured set of functionalities and design drivers...... required from the turbine DC converter and uses these to compare 6 distinct candidate circuit topologies. The end goal is not to select the best topology, but to narrow down from a vast list of options and give a method that will increase confidence and guide towards the characteristics of reliable design....

  10. Required coefficient of friction during turning at self-selected slow, normal, and fast walking speeds.

    Science.gov (United States)

    Fino, Peter; Lockhart, Thurmon E

    2014-04-11

    This study investigated the relationship of required coefficient of friction to gait speed, obstacle height, and turning strategy as participants walked around obstacles of various heights. Ten healthy, young adults performed 90° turns around corner pylons of four different heights at their self selected normal, slow, and fast walking speeds using both step and spin turning strategies. Kinetic data was captured using force plates. Results showed peak required coefficient of friction (RCOF) at push off increased with increased speed (slow μ=0.38, normal μ=0.45, and fast μ=0.54). Obstacle height had no effect on RCOF values. The average peak RCOF for fast turning exceeded the OSHA safety guideline for static COF of μ>0.50, suggesting further research is needed into the minimum static COF to prevent slips and falls, especially around corners. Copyright © 2014 Elsevier Ltd. All rights reserved.

  11. Data Qualification Report: Calculated Porosity and Porosity-Derived Values for Lithostratigraphic Units for use on the Yucca Mountain Project

    Energy Technology Data Exchange (ETDEWEB)

    P. Sanchez

    2001-05-30

    The qualification is being completed in accordance with the Data Qualification Plan DQP-NBS-GS-000006, Rev. 00 (CRWMS M&O 2001). The purpose of this data qualification activity is to evaluate for qualification the unqualified developed input and porosity output included in Data Tracking Number (DTN) M09910POROCALC.000. The main output of the analyses documented in DTN M09910POROCALC.000 is the calculated total porosity and effective porosity for 40 Yucca Mountain Project boreholes. The porosity data are used as input to Analysis Model Report (AMR) 10040, ''Rock Properties Model'' (MDL-NBS-GS-000004, Rev. 00), Interim Change Notice [ICN] 02 (CRWMS M&O 2000b). The output from the rock properties model is used as input to numerical physical-process modeling within the context of a relationship developed in the AMR between hydraulic conductivity, bound water and zeolitic zones for use in the unsaturated zone model. In accordance with procedure AP-3.15Q, the porosity output is not used in the direct calculation of Principal Factors for post-closure safety or disruptive events. The original source for DTN M09910POROCALC.000 is a Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M&O) report, ''Combined Porosity from Geophysical Logs'' (CRWMS M&O 1999a and hereafter referred to as Rael 1999). That report recalculated porosity results for both the historical boreholes covered in Nelson (1996), and the modern boreholes reported in CRWMS M&O (1996a,b). The porosity computations in Rael (1999) are based on density-porosity mathematical relationships requiring various input parameters, including bulk density, matrix density and air and/or fluid density and volumetric water content. The main output is computed total porosity and effective porosity reported on a foot-by-foot basis for each borehole, although volumetric water content is derived from neutron data as an interim output. This qualification

  12. Data Qualification Report: Calculated Porosity and Porosity-Derived Values for Lithostratigraphic Units for use on the Yucca Mountain Project

    International Nuclear Information System (INIS)

    P. Sanchez

    2001-01-01

    The qualification is being completed in accordance with the Data Qualification Plan DQP-NBS-GS-000006, Rev. 00 (CRWMS M and O 2001). The purpose of this data qualification activity is to evaluate for qualification the unqualified developed input and porosity output included in Data Tracking Number (DTN) M09910POROCALC.000. The main output of the analyses documented in DTN M09910POROCALC.000 is the calculated total porosity and effective porosity for 40 Yucca Mountain Project boreholes. The porosity data are used as input to Analysis Model Report (AMR) 10040, ''Rock Properties Model'' (MDL-NBS-GS-000004, Rev. 00), Interim Change Notice [ICN] 02 (CRWMS M and O 2000b). The output from the rock properties model is used as input to numerical physical-process modeling within the context of a relationship developed in the AMR between hydraulic conductivity, bound water and zeolitic zones for use in the unsaturated zone model. In accordance with procedure AP-3.15Q, the porosity output is not used in the direct calculation of Principal Factors for post-closure safety or disruptive events. The original source for DTN M09910POROCALC.000 is a Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M and O) report, ''Combined Porosity from Geophysical Logs'' (CRWMS M and O 1999a and hereafter referred to as Rael 1999). That report recalculated porosity results for both the historical boreholes covered in Nelson (1996), and the modern boreholes reported in CRWMS M and O (1996a,b). The porosity computations in Rael (1999) are based on density-porosity mathematical relationships requiring various input parameters, including bulk density, matrix density and air and/or fluid density and volumetric water content. The main output is computed total porosity and effective porosity reported on a foot-by-foot basis for each borehole, although volumetric water content is derived from neutron data as an interim output. This qualification report uses

  13. Advanced qualification techniques

    International Nuclear Information System (INIS)

    Winokur, P.S.; Shaneyfelt, M.R.; Meisenheimer, T.L.; Fleetwood, D.M.

    1993-01-01

    This paper demonstrates use of the Qualified Manufacturers List (QML) methodology to qualify commercial and military microelectronics for use in space applications. QML ''builds in'' the hardness of product through statistical process control (SPC) of technology parameters relevant to the radiation response, test structure to integrated circuit (IC) correlations, and techniques for extrapolating laboratory test results to low-dose-rate space scenarios. Each of these elements is demonstrated and shown to be a cost-effective alternative to expensive end-of-line IC testing. Several examples of test structured-IC correlations are provided and recent work on complications arising from transistor scaling and geometry is discussed. The use of a 10-keV x-ray wafer-level test system to support SPC and establish ''process capability'' is illustrated and a comparison of 10-keV x-ray and Co 60 gamma irradiations is provided for a wide range of CMOS technologies. The x-ray tester is shown to be cost-effective and its use in lot acceptance/qualification is recommended. Finally, a comparison is provided between MIL-STD-883D, Test Method 1019.4, which governs the testing of packaged semiconductor microcircuits in the DoD, and ESA/SSC Basic Specification No. 22900, Europe's Total Dose Steady-State Irradiation Test Method. Test Method 1019.4 focuses on conservative estimates of MOS hardness for space and tactical applications, while Basic Specification 22900 focuses on improved simulation of low-dose-rate space environments

  14. Instrumentation qualification. Seismic qualification of C-E instrumentation equipment. Part One

    International Nuclear Information System (INIS)

    1977-05-01

    A summary of the C-E seismic qualification program utilized to demonstrate the seismic design adequacy of the instrumentation and control equipment used in C-E supplied Nuclear Steam Supply Systems (NSSS) is presented. The report is divided into two parts. Part One includes the equipment seismic requirements and a description of the qualification methods. Part Two lists the specific equipment by nuclear station in which it is used and the equipment test results are summarized in a standard data sheet format to facilitate review. The seismic requirements are based on individual contract commitments with C-E customers and the NRC Standard Review Plan, Section 3.10 ''Seismic Qualification of Category I Instrumentation and Electrical Equipment.'' Equipment is qualified for use in a seismic environment where damage potential to the equipment is less than or equal to that simulated seismic environment to which it has been qualified. The anticipated Safe Shutdown Earthquake (SSE) environment at the inservice location of equipment should be confirmed by each applicant as not exceeding that to which it is qualified

  15. Qualification tests for PWR control element drive mechanism

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In Yong; Jin, Choon Eon; Choi Suhn [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-01-01

    It is necessary to perform the qualification test for the magnetic jack type CEDM to show the design compatibility because the CEDM is composed of many mechanical and electrical components complicatedly. ABB-CE performed various qualification tests during the development of the System80 CEDM to which Korea Standard Nuclear Plant (KSNP) CEDM referred. The qualification test for the CEDM is classified into the performance test and the dynamic test. The performance test is to verify operability of the CEDM, and the dynamic test is to find dynamic characteristics and to verify the structural integrity if the CEDM for the seismic accidents. Described in this report are the test requirements, the test facilities and the test methods for the performance and the dynamic qualification tests of the PWR magnetic jack type CEDM. The impacts of the design changes in the Korea Next Generation Reactor (KNGR) on the KSNP CEDM were analyzed to present the necessity for the tests. This report also proposes the facilities to perform the tests in KAERI including reasonable schedule for the tests. Attached to this report is the summary of qualification tests of System 80 CEDM performed by ABB-CE. 20 figs., 16 tabs., 21 refs. (Author) .new.

  16. Qualification tests for PWR control element drive mechanism

    International Nuclear Information System (INIS)

    Kim, In Yong; Jin, Choon Eon; Choi Suhn

    1996-01-01

    It is necessary to perform the qualification test for the magnetic jack type CEDM to show the design compatibility because the CEDM is composed of many mechanical and electrical components complicatedly. ABB-CE performed various qualification tests during the development of the System80 CEDM to which Korea Standard Nuclear Plant (KSNP) CEDM referred. The qualification test for the CEDM is classified into the performance test and the dynamic test. The performance test is to verify operability of the CEDM, and the dynamic test is to find dynamic characteristics and to verify the structural integrity if the CEDM for the seismic accidents. Described in this report are the test requirements, the test facilities and the test methods for the performance and the dynamic qualification tests of the PWR magnetic jack type CEDM. The impacts of the design changes in the Korea Next Generation Reactor (KNGR) on the KSNP CEDM were analyzed to present the necessity for the tests. This report also proposes the facilities to perform the tests in KAERI including reasonable schedule for the tests. Attached to this report is the summary of qualification tests of System 80 CEDM performed by ABB-CE. 20 figs., 16 tabs., 21 refs. (Author) .new

  17. Strategy for Qualification of the Plutonium Immobilized Form

    International Nuclear Information System (INIS)

    Marra, J.C.; Marra, S.L.; Bibler, N.E.; Strachan, D.M.; Shaw, H.F.

    1998-01-01

    In order to dispose of a radioactive waste form in a federal high- level waste repository, a waste form qualification strategy and program must be developed. The waste form qualification program must include the acceptance specifications for the product, show how compliance with these specifications will be met, and then demonstrate compliance. An important element of this program is developing a measure to demonstrate product consistency. For the can- in-canister option, waste form qualification is needed not only for the Pu immobilized form but also for the high-level waste glass canister containing the Pu waste form. The latter will require close interaction and coordination with the U.S. Department of Energy - Office of Environmental Management (DOE-EM) who, through their contractor at the Savannah River Site (SRS), is the producer of the high-level waste form at the Defense Waste Processing Facility (DWPF). In this paper a waste form qualification strategy for the plutonium ceramic form is described that utilizes, as much as possible, the qualification strategy successfully used for vitrified high-level waste

  18. Europeans come together on qualification

    International Nuclear Information System (INIS)

    Whittle, J.

    1996-01-01

    Utilities operating nuclear power plants in Europe have formed the European Network for Inspection Qualification (ENIQ) to produce a common approach to demonstrating that non-destructive testing is capable providing the information to ensure the absence of significant defects in nuclear plants. Major developments over recent months have included the issue by ENIQ of a formal document defining the methodology for the conduct of qualification which sets out the principles that detailed systems, within an individual country context, should embody. A pilot study on pipe welds typical of those in BWR recirculation loops is being conducted to explore the issues involved in the practical application of the methodology. In parallel with ENIQ, the European Nuclear Regulators Working Group has set up a Task Force in an attempt to define a common regulatory position on non-destructive testing qualifications and has produced its own document which is wider in scope than that of ENIQ. (UK)

  19. IAEA activities on NPP personnel training and qualification

    International Nuclear Information System (INIS)

    Kossilov, A.

    1998-01-01

    Activities of IAEA concerning training and qualification of NPP personnel consider the availability of sufficient number of competent personnel which is one of the most critical requirements for safe and reliable NPP operation and maintenance. Competence of personnel is essential for reducing the frequency of events connected to human errors and equipment failures. The IAEA Guidebook on Nuclear Power Plant Personnel Training and its Evaluation incorporates the experience gained worldwide and provides recommendations on the use of SAT being the best practice for attaining and maintaining the qualification and competence of NPP personnel and for quality assurance of training

  20. IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

  1. Qualification of box HEPA filters for nuclear applications

    International Nuclear Information System (INIS)

    Bergman, W.; Larsen, G.; Wilson, K.; Rainer, F.

    1995-03-01

    We have successfully completed qualification tests on high efficiency particulate air (HEPA) filters that are encapsulated within a box and manufactured by American Air Filters. The qualification tests are required by the American Society of Mechanical Engineers Standard ASME N509 and the U.S. Military Standard MIL-F-51068 for HEPA filters to be used in nuclear applications. The qualification tests specify minimum filter efficiencies following exposure to heated air, overpressure, and rough handling. Prior to this study, no box HEPA filters from any manufacturer had been qualified despite their wide-spread use in Department of Energy (DOE) facilities. Box HEPA filters are not addressed in any of the existing HEPA standards and only briefly discussed in the Nuclear Air Cleaning Handbook

  2. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  3. Nuclear criticality safety specialist training and qualification programs

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1993-01-01

    Since the beginning of the Nuclear Criticality Safety Division of the American Nuclear Society (ANS) in 1967, the nuclear criticality safety (NCS) community has sought to provide an exchange of information at a national level to facilitate the education and development of NCS specialists. In addition, individual criticality safety organizations within government contractor and licensed commercial nonreactor facilities have developed training and qualification programs for their NCS specialists. However, there has been substantial variability in the content and quality of these program requirements and personnel qualifications, at least as measured within the government contractor community. The purpose of this paper is to provide a brief, general history of staff training and to describe the current direction and focus of US DOE guidance for the content of training and qualification programs designed to develop NCS specialists

  4. Oct1 and OCA-B are selectively required for CD4 memory T cell function.

    Science.gov (United States)

    Shakya, Arvind; Goren, Alon; Shalek, Alex; German, Cody N; Snook, Jeremy; Kuchroo, Vijay K; Yosef, Nir; Chan, Raymond C; Regev, Aviv; Williams, Matthew A; Tantin, Dean

    2015-11-16

    Epigenetic changes are crucial for the generation of immunological memory. Failure to generate or maintain these changes will result in poor memory responses. Similarly, augmenting or stabilizing the correct epigenetic states offers a potential method of enhancing memory. Yet the transcription factors that regulate these processes are poorly defined. We find that the transcription factor Oct1 and its cofactor OCA-B are selectively required for the in vivo generation of CD4(+) memory T cells. More importantly, the memory cells that are formed do not respond properly to antigen reencounter. In vitro, both proteins are required to maintain a poised state at the Il2 target locus in resting but previously stimulated CD4(+) T cells. OCA-B is also required for the robust reexpression of multiple other genes including Ifng. ChIPseq identifies ∼50 differentially expressed direct Oct1 and OCA-B targets. We identify an underlying mechanism involving OCA-B recruitment of the histone lysine demethylase Jmjd1a to targets such as Il2, Ifng, and Zbtb32. The findings pinpoint Oct1 and OCA-B as central mediators of CD4(+) T cell memory. © 2015 Shakya et al.

  5. Biology and thermal requirements to Trichogramma spp. selection for Ecdytolopha aurantiana control

    International Nuclear Information System (INIS)

    Molina, Rosa M.S.; Parra, Jose R.P.

    2005-01-01

    The purpose of this work was to evaluate the potential of Trichogramma atopovirilia Oatman and Platner, 1983 and T. pretiosum Riley, 1879 as agents of control of Ecdytolopha aurantiana (Lima, 1927) (Lepidoptera: Tortricidae), an important Citrus pest in Sao Paulo State (South-East Brazil). In order to provide subsidies to programs of biological control with these parasitoids, studies of biology in different temperatures, thermal requirements and parasitism capacity were carried out. The temperatures (18, 20, 22, 25, 28, 30, and 32 deg C) did not affect the sex ratio, however, female longevity of both species was higher at 22 and 25 deg C. The temperature of 25 deg C tended to be more suitable to both emergency rate and female longevity. The egg-adult period for both Trichogramma species was inversely proportional to temperature. The thermal requirements of the two species were very close, about 108 DD (degree days). Neither the natural rearing host, E. aurantiana, nor the alternative host Anagasta kuehniella (Zeller, 1879) (Lepidoptera, Pyralidae), affected the number of parasitized eggs per Trichogramma female. The parasitism rate and the number of emerged adults per egg on E. aurantiana eggs were higher than on A. kuehniella eggs. However, the emergency rate was higher when the parasitoids were reared on A. kuehniella eggs. Both Trichogramma species could be tested in the field for citrus fruit borer control. The thermal requirements and the parasitism capacity also could be good parameters for selection of Trichogramma species/strains. (author)

  6. 78 FR 62935 - Qualification of Drivers; Exemption Applications; Vision

    Science.gov (United States)

    2013-10-22

    ..., his optometrist noted, ``Mr. Smith, despite having a prosthetic left eye, has fully functional vision...-0166] Qualification of Drivers; Exemption Applications; Vision AGENCY: Federal Motor Carrier Safety... announces receipt of applications from 26 individuals for exemption from the vision requirement in the...

  7. 78 FR 37273 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-06-20

    ...-2013-0016] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... achieved by complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving... mellitus currently requiring insulin for control'' (49 CFR 391.41(b)(3)). FMCSA established its diabetes...

  8. 77 FR 75493 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-12-20

    ...-2012-0282] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  9. 78 FR 26422 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-05-06

    ...-2013-0012] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... achieved by complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving... mellitus currently requiring insulin for control'' (49 CFR 391.41(b)(3)). FMCSA established its diabetes...

  10. 77 FR 65929 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-10-31

    ...-2012-0219] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  11. 77 FR 70529 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-11-26

    ...-2012-0281] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  12. 77 FR 75492 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-12-20

    ...-2012-0283] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the Applicants... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  13. 77 FR 38383 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-06-27

    ...-2012-0107] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the Applicants The... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  14. 78 FR 35088 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-06-11

    ...-2013-0015] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... would be achieved by complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and... of diabetes mellitus currently requiring insulin for control'' (49 CFR 391.41(b)(3)). FMCSA...

  15. 77 FR 64585 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-10-22

    ...-2012-0218] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the Applicants The... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  16. 77 FR 46791 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-08-06

    ...-2012-0162] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  17. 78 FR 5559 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-01-25

    ...-2012-0348] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  18. 78 FR 39825 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-07-02

    ...-2013-0018] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... diagnosis of diabetes mellitus currently requiring insulin for control'' [49 CFR 391.41(b)(3)]. FMCSA... Congress on the Feasibility of a Program to Qualify Individuals with Insulin-Treated Diabetes Mellitus to...

  19. 77 FR 33264 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-06-05

    ...-2012-0044] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  20. 77 FR 59450 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-09-27

    ...-2012-0164] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving Experience of the Applicants The... person has no established medical history or clinical diagnosis of diabetes mellitus currently requiring...

  1. 78 FR 37272 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-06-20

    ...-2013-0017] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... achieved by complying with the current regulation 49 CFR 391.41(b)(3). Diabetes Mellitus and Driving... mellitus currently requiring insulin for control'' (49 CFR 391.41(b)(3)). FMCSA established its diabetes...

  2. Qualification of software and hardware

    International Nuclear Information System (INIS)

    Gossner, S.; Schueller, H.; Gloee, G.

    1987-01-01

    The qualification of on-line process control equipment is subdivided into three areas: 1) materials and structural elements; 2) on-line process-control components and devices; 3) electrical systems (reactor protection and confinement system). Microprocessor-aided process-control equipment are difficult to verify for failure-free function owing to the complexity of the functional structures of the hardware and to the variety of the software feasible for microprocessors. Hence, qualification will make great demands on the inspecting expert. (DG) [de

  3. Qualification Practices in Nuclear Industry: Steam Generator Eddy Current Probe Qualification

    International Nuclear Information System (INIS)

    Vavrous, M.; Gracin, R.

    2010-01-01

    Through history of nuclear power plant operation, a large number of nuclear power plant forced outages related to tube failures occurred. It resulted with large amount of repair and outage costs, what initiated implementation of regulated practice of periodical tube examination and tube condition monitoring. Purpose of examinations is to detect existing or potential tube degradations that could affect tube integrity and therefore result in forced outages and unwanted costs related to emergency repair activities and loss of ability for electrical power production. With increased examination activities, additional information about steam generator tube condition became available and additional methods for ensuring tube integrity became available. As the number of examination solutions increased, need for validation and assessment of examination methods occurred. For that purpose, a large number of standards and guidelines with its requirements were implemented in nuclear industry regulatory requirements to ensure that adequately validated examinations are applied. With this purpose, qualification requirements for inspection activities were implemented with other requirements. With progress of technology, progress was also achieved in examination methods and more advanced examination methods and advanced inspection systems were developed. This advancement is accompanied by advancement in regulatory requirements regarding inspection and monitoring of tube integrity and condition. Ultimate goal of implementation of qualification processes and its requirements in all aspects of nuclear industry is to achieve minimal rate of forced outages, which would ensure maximum electrical power production capabilities and maximum optimization of operational costs while maintaining safe operation in accordance with environmental policies. This article will focus on qualification of steam generator eddy current bobbin probe.(author).

  4. 5 CFR 319.302 - Individual qualifications.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Individual qualifications. 319.302... Individual qualifications. Agency heads are delegated authority to approve the qualifications of individuals appointed to SL and ST positions. The agency head must determine that the individual meets the...

  5. Changing existing qualifications into outcomes-based qualifications ...

    African Journals Online (AJOL)

    Various workshops were facilitated to determine the outcomes of each level of our qualification, B Tech: Policing. This led to the formulation of a purpose statement, exit level outcomes and specific outcomes as well as assessment criteria and the critical outcomes embedded in each level identified. Using the specific ...

  6. Skill qualifications in pediatric minimally invasive surgery.

    Science.gov (United States)

    Iwanaka, Tadashi; Morikawa, Yasuhide; Yamataka, Atsuyuki; Nio, Masaki; Segawa, Osamu; Kawashima, Hiroshi; Sato, Masahito; Terakura, Hirotsugu; Take, Hiroshi; Hirose, Ryuichiro; Yagi, Makoto

    2011-07-01

    In 2006, The Japanese Society of Pediatric Endoscopic Surgeons devised a plan to develop a pediatric endoscopic surgical skill qualification (ESSQ) system. This system is controlled by The Japan Society for Endoscopic Surgery. The standard requirement for skills qualification is the ability of each applicant to complete common types of laparoscopic surgery. The main goal of the system is to decrease complications of laparoscopic surgery by evaluating the surgical skills of each applicant and subsequently certify surgeons with adequate skills to perform laparoscopic operations safely. A committee of pediatric ESSQ created a checklist to assess the applicant's laparoscopic surgical skills. Skills are assessed in a double-blinded fashion by evaluating an unedited video recording of a fundoplication for pediatric gastroesophageal reflux disease. The initial pediatric ESSQ system was started in 2008. In 2008 and 2009, respectively, 9 out of 17 (53%) and 6 out of 12 (50%) applicants were certified as expert pediatric laparoscopic surgeons. Our ultimate goal is to provide safe and appropriate pediatric minimally invasive procedures and to avoid severe complications. To prove the predictive validity of this system, a survey of the outcomes of operations performed by certified pediatric surgeons is required.

  7. Astronaut suitability requirements and selection process; Uchu hikoshi tanjo eno michi (shishitsu yokyu)

    Energy Technology Data Exchange (ETDEWEB)

    Miyoshi, H. [National Space Development Agency of Japan, Tokyo (Japan)

    1999-10-05

    Manned space activities at National Space Development Agency of Japan and the suitability requirements that an astronaut is supposed to satisfy are described. At the first phase, candidates have to participate in a manned space experiment utilizing a NASA space shuttle and, in 1985, Mori, Mukai, and Doi were selected to be payload specialists. At the second phase, Astronauts Wakata, Doi, and Mori were sent to the mission specialist training course, this being one of the jobs aboard a space shuttle, which was for preparing for the construction and operation of the international space station. In January, 1996, Astronaut Wakata performed extravehicular tool manipulation and so forth, and Astronaut Doi did the same in 1997. The endowments that an astronaut is expected to have include undoubted professionalism, adaptability to branches out of his field, adaptability to a prolonged stay in space, spirit of teamwork and coordination, and ability to perform wide range of duties aboard an international space station. (NEDO)

  8. Phosphate Sorption Characteristics and External P Requirements of Selected South African Soils

    Directory of Open Access Journals (Sweden)

    E. M. Gichangi

    2008-10-01

    Full Text Available The Transkei is the largest consolidated area in South Africa where land is held by smallholder farmers but little is known about the extent of phosphate fixation in the region. This study was conducted to determine the phosphate sorption properties and external P requirements (EPR of selected soils from the Transkei region, South Africa and to relate derived sorption values to selected soil parameters. The P sorption maxima and EPR values varied widely ranging from 192.3 to 909.1 mg P kg−1 and from 2 to 123 mg P kg−1−1 soil, respectively. Citrate dithionite bicarbonate-extractable aluminum explained most of the observed variations in P sorption. About 43% of the soils were found to be moderate P fixers and may need management interventions to ensure adequate P availability to crops. The single point sorption index accurately predicted the EPR of the soils obviating the need to use multiple point sorption isotherms. The results suggested that the use of blanket phosphate fertilizer recommendations may not be a good strategy for the region as it may lead to under-application or over-application of P in some areas.

  9. Selection for high and low oxygen consumption-induced differences in maintenance energy requirements of mice.

    Science.gov (United States)

    Darhan, Hongyu; Kikusato, Motoi; Toyomizu, Masaaki; Roh, Sang-Gun; Katoh, Kazuo; Sato, Masahiro; Suzuki, Keiichi

    2017-07-01

    Maintenance energy requirements (MER) of mice selected for high (H) or low (L) oxygen consumption (OC) were compared. Forty-four mice from H and L OC lines were weaned at 3 weeks and divided into four experimental groups: group A were sacrificed at 4 weeks; group B were fed ad libitum, and groups C and D were fed 2.8 and 2.4 g/day, respectively, from 4 to 8 weeks of age. Groups B-D were sacrificed at 8 weeks. Chemical components were estimated for all groups. MER was estimated using a model that partitioned metabolizable energy intake into that used for maintenance, and protein and fat deposition. The feed conversion ratio for the B group was significantly higher in the H than in the L line. Feed intake for metabolic energy content per metabolic body size was significantly also higher in the H line, whereas accumulated energy content per metabolic body size was significantly higher in the L line. MER of the H line was greater than that of the L line (P < 0.10). These results suggest that selection for H or L OC produced differences in chemical components, feed efficiency, and MER between the H and L lines. © 2016 Japanese Society of Animal Science.

  10. Unresolved Safety Issue A-46 - seismic qualification of equipment in operating plants

    International Nuclear Information System (INIS)

    Anderson, N.

    1985-01-01

    Seismic Qualification of Equipment in Operating Plants was designated as an Unresolved Safety Issue (USI) in December, 1980. The USI A-46 program was developed in early 1981 to investigate the adequacy of mechanical and electrical equipment in operating plants to withstand a safe shutdown earthquake. The approach taken was to develop viable, cost effective alternatives to current seismic qualification licensing requirements which could be applied to operating nuclear power plants. The tasks investigated include: (1) identification of seismic sensitive systems and equipment; (2) assessment of adequacy of existing seismic qualification methods; (3) development and assessment of in-situ test procedures to assist in qualification of equipment; (4) seismic qualification of equipment using seismic experience data; and (5) development of methods to generate generic floor response spectra. Progress to date and plans for completion of resolution are reported

  11. Mutual Recogniton of Professional Qualifications

    DEFF Research Database (Denmark)

    Enemark, Stig; Plimmer, Francis

    The publication aims to review the concept of mutual recognition of qualifications within the world wide surveying community, and to develop a framework for the introduction of standards of global professional competence in this area. The publication also includes a number of case studies from...

  12. Helicopter-Ship Qualification Testing

    NARCIS (Netherlands)

    Hoencamp, A.

    2015-01-01

    The goal of this research project is to develop a novel test methodology which can be used for optimizing cost and time efficiency of helicopter-ship qualification testing without reducing safety. For this purpose, the so-called “SHOL-X” test methodology has been established, which includes the

  13. Personnel Officers: Judging Their Qualifications.

    Science.gov (United States)

    Webb, Gisela

    1988-01-01

    Discusses the backgrounds and qualifications appropriate for a library personnel administrator, including (1) a master's degree in library science; (2) library work experience; (3) additional training in administration, personnel management, organizational development, and psychology; and (4) personal attributes such as good communication skills,…

  14. 77 FR 59339 - Contractor Qualifications

    Science.gov (United States)

    2012-09-27

    ... DEPARTMENT OF DEFENSE Defense Acquisition Regulations System 48 CFR Part 209 Contractor Qualifications CFR Correction In Title 48 of the Code of Federal Regulations, Chapter 2 (Parts 201-299), revised as of October 1, 2011, on page 55, in section 209.104-70, paragraph (a) is amended by revising the...

  15. Seismic and dynamic qualification methods

    International Nuclear Information System (INIS)

    Lin, C.W.

    1985-01-01

    This book presents the papers given at a conference on seismic effects on nuclear power plants. Topics considered at the conference included seismic qualification of equipment, multifrequency test methodologies, damping in piping systems, the amplification factor, thermal insulation, welded joints, and response factors for seismic risk analysis of piping

  16. The ASEAN economic community and medical qualification.

    Science.gov (United States)

    Kittrakulrat, Jathurong; Jongjatuporn, Witthawin; Jurjai, Ravipol; Jarupanich, Nicha; Pongpirul, Krit

    2014-01-01

    In the regional movement toward ASEAN Economic Community (AEC), medical professions including physicians can be qualified to practice medicine in another country. Ensuring comparable, excellent medical qualification systems is crucial but the availability and analysis of relevant information has been lacking. This study had the following aims: 1) to comparatively analyze information on Medical Licensing Examinations (MLE) across ASEAN countries and 2) to assess stakeholders' view on potential consequences of AEC on the medical profession from a Thai perspective. To search for relevant information on MLE, we started with each country's national body as the primary data source. In case of lack of available data, secondary data sources including official websites of medical universities, colleagues in international and national medical student organizations, and some other appropriate Internet sources were used. Feasibility and concerns about validity and reliability of these sources were discussed among investigators. Experts in the region invited through HealthSpace.Asia conducted the final data validation. For the second objective, in-depth interviews were conducted with 13 Thai stakeholders, purposely selected based on a maximum variation sampling technique to represent the points of view of the medical licensing authority, the medical profession, ethicists and economists. MLE systems exist in all ASEAN countries except Brunei, but vary greatly. Although the majority has a national MLE system, Singapore, Indonesia, and Vietnam accept results of MLE conducted at universities. Thailand adopted the USA's 3-step approach that aims to check pre-clinical knowledge, clinical knowledge, and clinical skills. Most countries, however, require only one step. A multiple choice question (MCQ) is the most commonly used method of assessment; a modified essay question (MEQ) is the next most common. Although both tests assess candidate's knowledge, the Objective Structured Clinical

  17. Method for qualification of cementation processes and its application to a vibration mixer

    International Nuclear Information System (INIS)

    Vicente, R.; Rzyski, B.M.; Suarez, A.A.

    1987-01-01

    In this paper the definition of homogeneneity is discussed and methods to measure the 'degree of heterogeneity' of waste forms are proposed. These measurements are important as aids for mixing process qualification, and as tools in quality assurance procedures and in the development of waste management standards. Homogeneity is a basic quality requirement for waste forms to be accepted in final sites. It do not depend on the matrix immmobilization, rather it is one mean for qualification of the immobilization process. The proposed methods were applied to a vibration assisted mixing process and has proved to an useful mean to judge process improvements. There are many conceivable methods to evaluate homogeneity of waste forms. Some were selected as screening tests aiming at quickly reaching a promising set of process variables. Others were selected to evaluate the degree of excellence of the process in respect to product quality. These envisaged methods were: visual inspection, the use of cement dye as tracer, scanning of radioactive tracers, and measurements of variations of density, water absorption, porosity and mechanical strength across the waste form sample. The process variables were: waste-cement and water-cement ratios, mixer geometry, mixing time and vibration intensity. Some of the apparatus details were change during the experimental work in order to improve product quality. Experimental methods and results statistically analysed and compared with data obtained from samples prepared with a planetary paddle mixer, which were adopted as the homogeneity standard. (Author) [pt

  18. 20 CFR 670.420 - Are there any special requirements for enrollment related to the Military Selective Service Act?

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Are there any special requirements for enrollment related to the Military Selective Service Act? 670.420 Section 670.420 Employees' Benefits... INVESTMENT ACT Recruitment, Eligibility, Screening, Selection and Assignment, and Enrollment § 670.420 Are...

  19. IEEE Std 382-1985: IEEE standard for qualification of actuators for power operated valve assemblies with safety-related functions for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions Part I describes the qualification process. Part II describes the standard qualification cases and their environmental parameters for the usual locations of safety-related equipment in a nuclear generating station. Part III describes the qualification tests outlined in 6.3.3

  20. Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6 

    Energy Technology Data Exchange (ETDEWEB)

    P.L. Cloke

    2001-10-16

    The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities.

  1. Environmental qualification program for Krsko NPP

    International Nuclear Information System (INIS)

    Cerjak, J.; Klenovsek, P.; Pavsek, J.; Freeland, K.R.; Spalj, S.

    1998-01-01

    NEK plant components, including those critical to safe plant operation, deteriorate and wear over service life due to the effects of aging and harsh environmental conditions. Since the plant environment is a source of common-cause failures, an Environmental Qualification (EQ) program is required to ensure and demonstrate the ability of safety-related equipment to perform its design safety function during a design-basis (DBE), even after aging over its service life in the plant. EQ is a requirement for plants licensed by the US NRC, in accordance with 10 CFR 50.49, Regulatory Guide 1.89, NUREG-0588, and IEEE-323. This paper presents the current EQ Program status at Krsko NPP.(author)

  2. Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2

    International Nuclear Information System (INIS)

    Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A.; Naranjo U, J. L.

    2013-10-01

    This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

  3. Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

    Energy Technology Data Exchange (ETDEWEB)

    Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

    2013-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

  4. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2000-01-01

    In 1999 the Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on the overall training system and on developing programmes for individual categories for NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce and SE-VYZ. The fundamental theoretical and periodical training for both Bohunice and Mochovce NPPs personnel, simulator training for NPP Bohunice, and periodical simulator training for Bohunice personnel is carried out by the VUJE Training center in Trnava, whereas the simulator training and periodical training for NPP Mochovce is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues, a certificate on special professional skills of selected staff of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: (a)Shift manager for scientific start up with the right of manipulation; (b) Shift supervisor; (c) Unit supervisor; (d) Primary circuit operator; (e) Secondary circuit operator; (f) Reactor physicist; (g) Shift manager for scientific start up without the right of manipulation. Examination of selected personnel is described. Last year the examining committee held twelve session for oral theoretical examination. The number of licenses issued in 1999 and the total number of valid licenses is given.Conclusions from inspections carried out by UJD and inspections and tests carried out by the NPP operators in 1999, as well as results from operation and start up of nuclear units confirm that the standard of professional skills of the staff at nuclear installations a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for the staff for 1999. These training, composed of specialized qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organized

  5. Teachers' Educational Qualification, Rank Level, Working Duration, Age, Work Motivation and Work Effectiveness

    OpenAIRE

    Wiyono, Bambang Budi

    2009-01-01

    Teachers’ Educational Qualification, Rank Level, Working Duration, Age, Working Mo­tivation, and Working Effectiveness The study investigated the effects of educational qualification, rank level, working duration and age on the elementary school teachers’ working motivation and working ef­fectiveness. The sample of the study consisted of 438 elementary school teachers in Malang which were selected through cluster sampling technique. The study was conducted using explanatory design in the form...

  6. [Anthropometrical profile of Brazilian junior volleyball players for different sports requirement levels].

    Science.gov (United States)

    Fonseca-Toledo, Cláudio; Roquetti, Paula; Fernandes-Filho, José

    2010-12-01

    This study was aimed at investigating the anthropometrics characteristics of male Brazilian junior volleyball players, organised into 3 sports requirement groups: high qualification (HQ) formed by the national team, middle qualification (MQ) formed by athletes playing in the Brazilian national championships and low qualification (LQ) formed by players at school level. 101 athletes were observed, HQ (n=16), MQ (n=68) and LQ (n=17), aged 16.7 ± 0.5; 16.6 ± 0.5 and 16.2 ± 0.7 years, respectively. There following were evaluated: body mass, height, standing reach height, % body fat and Heath & Carter somatotype. The statistical analysis was descriptive and inferential, the Kruskal Wallis test being used for detecting differences between groups (pcharacteristics and requirement levels, considering psports' selection instrument for young talented volleyball players.

  7. Design and qualification of a RTOS for safety class nuclear C and I applications

    International Nuclear Information System (INIS)

    Wakankar, A.; Khan, Arindam; Kalra, Mohit; Mitra, Raka; Aravamuthan, G.; Bhattacharjee, A.K.; Vaidya, U.W.; Mayya, Anuradha

    2014-01-01

    Real Time Operating System (RTOS) is a critical component of embedded systems. International standards such as IEC60880 used for development of Instrumentation and Control (I and C) system in nuclear power plants require rigorous qualification of all software components. In this paper, we describe our experience in the design and qualification of ESOS; an in-house configured RTOS from a commodity RTOS available with source code. The qualification activities include static and dynamic analysis, timing analysis and rigorous program analysis. We discuss how rigorous program analysis was used to uncover a subtle bug in the implementation. We also discuss the applications where this qualified RTOS has been successfully used. (author)

  8. Qualification criteria to certify a package for air transport of plutonium

    International Nuclear Information System (INIS)

    1977-12-01

    The document describes qualification criteria developed by the U.S. Nuclear Regulatory Commission to certify a package for air transport of plutonium. Included in the document is a discussion of aircraft accident conditions and a summary of the technical basis for the qualification criteria. The criteria require prototype packages to be subjected to various individual and sequential tests that simulate the conditions produced in severe aircraft accidents. Specific post-test acceptance standards are prescribed for each of the three safety functions of a package. The qualification criteria also prescribe certain operational controls to be exercised during transport

  9. 'Outside the box thinking': An overview of an environmental qualification test from a test lab perspective

    International Nuclear Information System (INIS)

    Mitton, T.

    2004-01-01

    Most people in the nuclear Environmental Qualification (EQ) business know that the basis for qualification ultimately lies with an equipment's successful operation during and after exposure to a simulated harsh environment. As opposed to focusing specifically on the test results of an Environmental Qualification test program, this paper/presentation will offer a more detailed look at the mechanical, electrical and thermodynamic requirements as well as the project difficulties and solutions of one such project - particularly an extensive, large-scale, non-typical project. (author)

  10. Lessons learned in the environmental qualification of class IE equipment at Tennessee Valley Authority

    International Nuclear Information System (INIS)

    Bell, R.N.; Akos, T.

    1985-01-01

    Tennessee Valley Authority has been engaged in an extensive program for the environmental qualification of Class 1E components. This program has been conducted in accordance with the requirements set forth in various industry standards and federal regulations, including IEEE 323-1971, IEEE 323-1974, Nuclear Regulatory Commission (NRC) IE Bulletin 7901B, NRC NUREG-0588, and the Code of Federal Regulations 10CFR50.49. Valuable lessons have been learned as a result of this program, particularly in the area of environmental qualification testing. This paper describes some unique experiences in the qualification testing of main steam isolation valve control manifold assemblies, control relays, and motor control centers

  11. Impact of pre-conditioning on the qualification of safety-related equipment

    International Nuclear Information System (INIS)

    Isgro, J.R.

    1982-01-01

    This paper shares some recent experiences on the effects of preconditioning on the qualification of safety-related equipment not located in a harsh environment. Environmental and seismic qualification testing programs were conducted following the guidelines of IEEE 323-1974, IEEE 344-1975 and appropriate IEEE daughter standards, where available. The examples that follow will illustrate the degree of pre-conditioning of safety-related equipment qualified to the requirements of IEEE-323-1974, and its effect on the outcome of the qualification program

  12. Process Qualification Strategy for Advances Embedded Non Volatile Memory Technology : The Philips' 0.18um Embedded Flash Case

    NARCIS (Netherlands)

    Tao, Guoqiao; Scarpa, Andrea; van Dijk, Kitty; Kuper, Fred G.

    2003-01-01

    A qualification strategy for advanced embedded non-volatile memory technology has been revealed. This strategy consists of: a thorough understanding of the requirements, extensive use and frequent update of the FMEA (failure mode effect analysis), a qualification plan with excellent coverage of all

  13. The qualification of electrical components and instrumentations relevant to safety

    International Nuclear Information System (INIS)

    Zambardi, F.

    1989-03-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  14. Sustained qualification process for full scope nuclear power plant simulators

    International Nuclear Information System (INIS)

    Pirson, J.; Stubbe, E.; Vanhoenacker, L.

    1994-01-01

    In the past decade, simulator training for all nuclear power plant operators has evolved into a vital requirement. To assure a correct training, the simulator qualification process is an important issue not only for the initial validation but also following major simulator updates, which are necessary during the lifetime of the simulator. In order to avoid degradation of the simulator validated software, the modifications have to be introduced according to a rigorous methodology and a practical requalification process has to be applied. Such methodology has to be enforced at every phase of the simulator construction or updating process from plant data package constitution, over simulator software development to simulator response qualification. The initial qualification and requalification process is based on the 3 levels identified by the ANSI/ANS 3-5 standard for steady-state, operational transients and accident conditions. For the initial certification of the full scope simulators in Belgium, a practical qualification methodology has been applied, which has been adapted into a set of non regression tests for the requalification after major simulator updates. (orig.) (4 refs., 3 figs.)

  15. Pilot study approach and qualification dossier components

    International Nuclear Information System (INIS)

    Ammirato, F.; Ashwin, P.

    2000-01-01

    The aim of the Pilot Project is to evaluate the IAEA Guidelines and methodology for the benefit of IAEA Member States trough a simulation of qualification activities. The Project is based on a real component and available data - NPP Kozloduy unit 5, weld 3. The initial phase is limited to the Qualification dossier. The Project relies on the input from the team members and Member States. Team organization and responsibilities are presented. The components of the Qualification Dossier (technical specification, inspection procedure and preliminary review, qualification procedure) and their current status are also presented. A comparison is done with their qualification programs. The characteristics of performance demonstrations are discussed. The results show that the teamwork has been successful and the IAEA methodology covers all situations. It is expected that the End Project will become 'Benchmark's' for future qualification activities

  16. Qualification of NDE personnel in the nuclear industry

    International Nuclear Information System (INIS)

    Epps, T.N.

    1984-01-01

    There has been evidence of ineffective programs for certifying nondestructive examination (NDE) personnel who conduct periodic inservice examinations in nuclear power plants under ASME Section XI Code requirements. This was brought to the attention of a group from the electric utility industry, the Electric Power Research Institute (EPRI), some NDE consultants and representatives from the American Society of Mechanical Engineers (ASME) by the Nuclear Regulatory Commission (NRC) in a May, 1982 meeting in Bethesda, Maryland. One problem pointed out by the NRC was the lack of a clear definition of qualification requirements for certification of NDE personnel who conduct ASME Section XI Inservice Inspection work in nuclear power plants. The NRC requested that the nuclear industry resolve this problem by formulating definitive qualification requirements for personnel certification that could be made an industry requirement. In June, 1982 the EPRI NDE Subcommittee held a general meeting for utility representatives to discuss the results of the May, 1982 meeting to develop a plan for industry response to the issue. The consensus was that an Ad Hoc Committee of utility representatives be convened to develop a document outlining qualification requirements for vertification of NDE personnel. The Ad Hoc Committee was formally convened on September 29, 1982

  17. AGR-1 Data Qualification Report

    International Nuclear Information System (INIS)

    Abbott, Michael

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office (TDO) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor experiment (AGR-1), the processing of these data within NDMAS, and reports the qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. They include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent quality assurance program. The NDMAS database processing and qualification status of the following five data streams is reported in this document: (1) Fuel fabrication data. All data have been processed into the NDMAS database and qualified (1,819 records). (2) Fuel irradiation data. Data from all 13 AGR-1 reactor cycles have been processed into the NDMAS database and tested. Of these, 85% have been qualified and 15% have failed NDMAS accuracy testing. (3) FPMS data. Reprocessed (January 2010) data from all 13 AGR-1 reactor cycles have been processed into the database and capture tested. Final qualification of these data will be recorded after QA approval of an Engineering Calculations and Analysis Report currently

  18. Response Variability in Commercial MOSFET SEE Qualification

    International Nuclear Information System (INIS)

    George, J. S.; Clymer, D. A.; Turflinger, T. L.; Mason, L. W.; Stone, S.

    2016-01-01

    Single-event effects (SEE) evaluation of five different part types of next generation, commercial trench MOSFETs indicates large part-to-part variation in determining a safe operating area (SOA) for drain-source voltage (V_D_S) following a test campaign that exposed >50 samples per part type to heavy ions. These results suggest a determination of a SOA using small sample sizes may fail to capture the full extent of the part-to-part variability. An example method is discussed for establishing a Safe Operating Area using a one-sided statistical tolerance limit based on the number of test samples. Finally, burn-in is shown to be a critical factor in reducing part-to-part variation in part response. Implications for radiation qualification requirements are also explored.

  19. Sensor Selection method for IoT systems – focusing on embedded system requirements

    Directory of Open Access Journals (Sweden)

    Hirayama Masayuki

    2016-01-01

    Full Text Available Recently, various types of sensors have been developed. Using these sensors, IoT systems have become hot topics in embedded system domain. However, sensor selections for embedded systems are not well discussed up to now. This paper focuses on embedded system’s features and architecture, and proposes a sensor selection method which is composed seven steps. In addition, we applied the proposed method to a simple example – a sensor selection for computer scored answer sheet reader unit. From this case study, an idea to use FTA in sensor selection is also discussed.

  20. ENIQ: European Network for Inspection Qualification

    International Nuclear Information System (INIS)

    Champigny, F.; Crutzen, S.; Lemaitre, P.

    1995-01-01

    Many countries are currently considering their own approach to inspection qualification and are carefully assessing experience to date. ENIQ, which stands for European Network for Inspection Qualification, groups the major part of the utilities in Western Europe. The general objective of ENIQ is to coordinate and manage at European level expertise and resources for the assessment and qualification of NDE inspection techniques and procedures, primarily for nuclear components. Also non-nuclear heavy duty components will be considered. Within ENIQ there is a growing consensus of opinion on the general principles of a European approach towards inspection qualification. In this paper the main activities, organization and actual status of ENIQ will be discussed

  1. Environmental requirements for flat plate photovoltaic modules for terrestrial applications

    Science.gov (United States)

    Hoffman, A. R.; Ross, R. G., Jr.

    1979-01-01

    The environmental test requirements that have been developed for flat plate modules purchased through Department of Energy funding are described. Concurrent with the selection of the initial qualification tests from space program experience - temperature cycling and humidity - surveys of existing photovoltaic systems in the field revealed that arrays were experiencing the following failure modes: interconnect breakage, delamination, and electrical termination corrosion. These coupled with application-dependent considerations led to the development of additional qualification tests, such as cyclic pressure loading, warped mounting surface, and hail. Rationale for the selection of tests, their levels and durations is described. Comparisons between field-observed degradation and test-induced degradation show a positive correlation with some of the observed field effects. Also, the tests are proving useful for detecting design, process, and workmanship deficiencies. The status of study efforts for the development of environmental requirements for field-related problems is reviewed.

  2. Australian Qualifications Framework Lower-Level Qualifications: Pathways to Where for Young People?

    Science.gov (United States)

    Stanwick, John

    2005-01-01

    This study investigates where certificate I and II qualifications lead young people aged 15-24 years in terms of employment and further study. A prime motivation for young people undertaking these qualifications is to facilitate transition into the labour market. These qualifications are aimed at developing basic vocational skills or preparatory…

  3. The Humanitarian Action Qualifications Framework: a quality assurance tool for the Humanitarian Sector

    Directory of Open Access Journals (Sweden)

    Bastiaan L. Aardema

    2014-07-01

    Full Text Available The article presents the European Universities on Professionalisation on Humanitarian Action (EUPRHA Project as an initiative that seeks to contribute to the professionalisation and quality assurance of the humanitarian sector. Its purpose is to explain the approach and the process leading to the development of the Humanitarian Action Qualifications Framework as an example of good practice for other sectors aiming at improving the recognition of qualifications as a precondition of academic and professional mobility. With this aim, it introduces the educational and humanitarian trends that led to this project: the move from transnational qualifications frameworks of which the European Qualifications Framework for Lifelong Learning (EQF is the best example to sectoral qualifications frameworks and the increasing demand from the sector seeking to determine the competencies and required skills of a professional humanitarian aid worker. Based on the EQF and the Tuning methodology the framework will act as a translating device to make national and sectoral qualifications more readable and promote humanitarian workers’ and learners’ mobility between countries and organisations. It will facilitate inter-system transparency and recognition of (non-formal and informal learning by linking occupations, skills, competences, and qualifications, thus benefiting the Humanitarian Sector as a whole.

  4. Modifications and additions to selected TOUGH2 modules

    International Nuclear Information System (INIS)

    Wu, Y.S.; Mishra, A.K.

    1998-01-01

    The purpose of this report is to provide all software baseline documents necessary for the software qualification of the revised versions of the selected TOUGH2 modules, which include single-phase gas (EOS1G), effective continuum method (EOS3/ECM), saturated/unsaturated flow (EOS9), and radionuclide transport (T2R3D) modules of the TOUGH2 code. TOUGH2 is a numerical simulation code for multi-dimensional, coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. This report augments the document Software Qualification of Selected TOUGH2 modules. This report contains the following sections: (1) requirement specifications and code development and (2) software validation test plan and results. These sections comprise sequential parts of Software Lifecycle, and should be used in conjunction with the TOUGH User's Guide, TOUGH2 documentation, TOUGH2 Software Qualification, and Software Qualification of Selected TOUGH2 modules. The version of TOUGH2 used with the software being qualified herein is the October 1996 Standard Version 1.2, as qualified in Wu et al. (1996) and housed at the Department of Energy's Energy Science and Technology Software Center (ESTSC) in Oak Ridge, Tennessee

  5. Student Computer Use in Selected Undergraduate Agriculture Courses: An Examination of Required Tasks.

    Science.gov (United States)

    Johnson, Donald M.; Ferguson, James A.; Vokins, Nancy W.; Lester, Melissa L.

    2000-01-01

    Over 50% of faculty teaching undergraduate agriculture courses (n=58) required use of word processing, Internet, and electronic mail; less than 50% required spreadsheets, databases, graphics, or specialized software. They planned to maintain or increase required computer tasks in their courses. (SK)

  6. Qualification Needs, Approaches and Strategies in the Second-Hand Sector A European Good Practice Report

    OpenAIRE

    Arold, Heike

    2008-01-01

    Against the background of changing consumer behaviour and environmental policies, a growing second-hand sector is expected. In order to ensure quality and professionalism within companies operating in this sector, it is necessary to develop a unified Europe-wide and sector-specific qualification which is geared to real working processes and requirements. This good practice report describes the training and qualification structures in the European second-hand sector. In addition, occupational ...

  7. IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard

  8. IEEE Std 382-1980: IEEE standard for qualification of safety-related valve actuators

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of all safety-related functions of power-driven valve actuators

  9. 46 CFR 68.7 - Qualification as an 883-1 corporation.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Qualification as an 883-1 corporation. 68.7 Section 68.7... Trade § 68.7 Qualification as an 883-1 corporation. (a) To be formally qualified as an 883-1 corporation for all purposes under the Act, a corporation which meets the requirements of § 68.5 must file with...

  10. Selective accumulation of biotin in arterial chemoreceptors: requirement for carotid body exocytotic dopamine secretion.

    Science.gov (United States)

    Ortega-Sáenz, Patricia; Macías, David; Levitsky, Konstantin L; Rodríguez-Gómez, José A; González-Rodríguez, Patricia; Bonilla-Henao, Victoria; Arias-Mayenco, Ignacio; López-Barneo, José

    2016-12-15

    Biotin, a vitamin whose main role is as a coenzyme for carboxylases, accumulates at unusually large amounts within cells of the carotid body (CB). In biotin-deficient rats biotin rapidly disappears from the blood; however, it remains at relatively high levels in CB glomus cells. The CB contains high levels of mRNA for SLC5a6, a biotin transporter, and SLC19a3, a thiamine transporter regulated by biotin. Animals with biotin deficiency exhibit pronounced metabolic lactic acidosis. Remarkably, glomus cells from these animals have normal electrical and neurochemical properties. However, they show a marked decrease in the size of quantal dopaminergic secretory events. Inhibitors of the vesicular monoamine transporter 2 (VMAT2) mimic the effect of biotin deficiency. In biotin-deficient animals, VMAT2 protein expression decreases in parallel with biotin depletion in CB cells. These data suggest that dopamine transport and/or storage in small secretory granules in glomus cells depend on biotin. Biotin is a water-soluble vitamin required for the function of carboxylases as well as for the regulation of gene expression. Here, we report that biotin accumulates in unusually large amounts in cells of arterial chemoreceptors, carotid body (CB) and adrenal medulla (AM). We show in a biotin-deficient rat model that the vitamin rapidly disappears from the blood and other tissues (including the AM), while remaining at relatively high levels in the CB. We have also observed that, in comparison with other peripheral neural tissues, CB cells contain high levels of SLC5a6, a biotin transporter, and SLC19a3, a thiamine transporter regulated by biotin. Biotin-deficient rats show a syndrome characterized by marked weight loss, metabolic lactic acidosis, aciduria and accelerated breathing with normal responsiveness to hypoxia. Remarkably, CB cells from biotin-deficient animals have normal electrophysiological and neurochemical (ATP levels and catecholamine synthesis) properties; however

  11. Qualification of flat welding of nuclear fuel bars

    International Nuclear Information System (INIS)

    Romero C, J.; Rivera M, H.

    2001-01-01

    The qualification of flat welding consists in the process (procedures (11), instructions (5), specifications (4) and programs (3)) and equipment (systems (4), equipment (6)) with the Personal Qualification (operators and supervisors) that was done in simultaneous form and supported with test and training programs with its respective technical reports, liberated by the Quality Assurance Office of ININ. Moreover, specific procedures of process and personal qualification are realized with the respective supervision by Quality Assurance Office. For the process, 20 welding were realized as follow: 5 welding with maximum contributing of heat, 10 welding with nominal contributing of heat, 5 welding with minimum contributing of heat. The heat contributing for the qualification was done maximum, of increasing the welding current, diminishing the helium flux and the revolutions per minute of the bar, at the moment of welding, with respect to nominal values. In the minimum contributing of heat it is diminished the welding current, increasing the helium flux and the revolutions per minute of the bar with respect to nominal values. With the qualification it has been finished the development of flat welding with results which define an own method of ININ. It was implemented a pneumatic system, for the elimination of micron cracks. It was required a control of turn velocity of the bar of hundredth of revolution. Moreover the main welding parameters each 40 μs are acquired. Also it was automated completely the process to avoid possible human mistakes. The standard deviations of the values of the realized inspections in the quality, are lower. Process, equipment and personnel with their respective Quality reports and registries are qualified, as well as the Quality certificates of two operators and one supervisor. (Author)

  12. Genomic selection needs to be carefully assessed to meet specific requirements in livestock breeding programs

    Directory of Open Access Journals (Sweden)

    Elisabeth eJonas

    2015-02-01

    Full Text Available Genomic selection is a promising development in agriculture, aiming improved production by exploiting molecular genetic markers to design novel breeding programs and to develop new markers-based models for genetic evaluation. It opens opportunities for research, as novel algorithms and lab methodologies are developed. Genomic selection can be applied in many breeds and species. Further research on the implementation of genomic selection in breeding programs is highly desirable not only for the common good, but also the private sector (breeding companies. It has been projected that this approach will improve selection routines, especially in species with long reproduction cycles, late or sex-limited or expensive trait recording and for complex traits. The task of integrating genomic selection into existing breeding programs is, however, not straightforward. Despite successful integration into breeding programs for dairy cattle, it has yet to be shown how much emphasis can be given to the genomic information and how much additional phenotypic information is needed from new selection candidates. Genomic selection is already part of future planning in many breeding companies of pigs and beef cattle among others, but further research is needed to fully estimate how effective the use of genomic information will be for the prediction of the performance of future breeding stock. Genomic prediction of production in crossbreeding and across-breed schemes, costs and choice of individuals for genotyping are reasons for a reluctance to fully rely on genomic information for selection decisions. Breeding objectives are highly dependent on the industry and the additional gain when using genomic information has to be considered carefully. This review synthesizes some of the suggested approaches in selected livestock species including cattle, pig, chicken and fish. It outlines tasks to help understanding possible consequences when applying genomic information in

  13. Qualification of phased array ultrasonic examination on T-joint weld of austenitic stainless steel for ITER vacuum vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, G.H. [ITER Korea, National Fusion Research Institute, Daejeon 305-333 (Korea, Republic of); Park, C.K., E-mail: love879@hanmail.net [ITER Korea, National Fusion Research Institute, Daejeon 305-333 (Korea, Republic of); Jin, S.W.; Kim, H.S.; Hong, K.H.; Lee, Y.J.; Ahn, H.J.; Chung, W. [ITER Korea, National Fusion Research Institute, Daejeon 305-333 (Korea, Republic of); Jung, Y.H.; Roh, B.R. [Hyundai Heavy Industries Co. Ltd., Ulsan 682-792 (Korea, Republic of); Sa, J.W.; Choi, C.H. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France)

    2016-11-01

    Highlights: • PAUT techniques has been developed by Hyundai Heavy Industries Co., LTD (HHI) and Korea Domestic Agency (KODA) to verify and settle down instrument calibration, test procedures, image processing, and so on. As the first step of development for PAUT technique, Several dozens of qualification blocks with artificial defects, which are parallel side drilled hole, embedded lack of fusion, embedded repair weld notch, and so on, have been designed and fabricated to simulate all potential defects during welding process. Real UT qualification group-1 for T-joint weld was successfully conducted in front of ANB inspector. • In this paper, remarkable progresses of UT qualification are presented for ITER vacuum vessel. - Abstract: Full penetration welding and 100% volumetric examination are required for all welds of pressure retaining parts of the ITER Vacuum Vessel (VV) according to RCC-MR Code and French Order of Nuclear Pressure Equipment (ESPN). The NDE requirement is one of important technical issues because radiographic examination (RT) is not applicable to many welding joints. Therefore the ultrasonic examination (UT) has been selected as an alternative method. Generally the UT on the austenitic welds is regarded as a great challenge due to the high attenuation and dispersion of the ultrasonic signal. In this paper, Phased array ultrasonic examination (PAUT) has been introduced on double sided T-shape austenitic welds of the ITER VV as a major NDE method as well as RT. Several dozens of qualification blocks with artificial defects, which are parallel side drilled hole, embedded lack of fusion, embedded repair weld notch, embedded parallel vertical notch, and so on, have been designed and fabricated to simulate all potential defects during welding process. PAUT techniques on the thick austenitic welds have been developed taking into account the acceptance criteria. Test procedure including calibration of equipment is derived and qualified through

  14. Analytical considerations in the code qualification of piping systems

    International Nuclear Information System (INIS)

    Antaki, G.A.

    1995-01-01

    The paper addresses several analytical topics in the design and qualification of piping systems which have a direct bearing on the prediction of stresses in the pipe and hence on the application of the equations of NB, NC and ND-3600 of the ASME Boiler and Pressure Vessel Code. For each of the analytical topics, the paper summarizes the current code requirements, if any, and the industry practice

  15. Qualification and certification of nondestructive testing personnel. Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    Aly, E A [Quality Assurance Department, national Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo, (Egypt)

    1996-03-01

    Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel.

  16. Qualification and certification of nondestructive testing personnel. Vol. 1

    International Nuclear Information System (INIS)

    Aly, E.A.

    1996-01-01

    Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel

  17. Genomic selection needs to be carefully assessed to meet specific requirements in livestock breeding programs.

    Science.gov (United States)

    Jonas, Elisabeth; de Koning, Dirk-Jan

    2015-01-01

    Genomic selection is a promising development in agriculture, aiming improved production by exploiting molecular genetic markers to design novel breeding programs and to develop new markers-based models for genetic evaluation. It opens opportunities for research, as novel algorithms and lab methodologies are developed. Genomic selection can be applied in many breeds and species. Further research on the implementation of genomic selection (GS) in breeding programs is highly desirable not only for the common good, but also the private sector (breeding companies). It has been projected that this approach will improve selection routines, especially in species with long reproduction cycles, late or sex-limited or expensive trait recording and for complex traits. The task of integrating GS into existing breeding programs is, however, not straightforward. Despite successful integration into breeding programs for dairy cattle, it has yet to be shown how much emphasis can be given to the genomic information and how much additional phenotypic information is needed from new selection candidates. Genomic selection is already part of future planning in many breeding companies of pigs and beef cattle among others, but further research is needed to fully estimate how effective the use of genomic information will be for the prediction of the performance of future breeding stock. Genomic prediction of production in crossbreeding and across-breed schemes, costs and choice of individuals for genotyping are reasons for a reluctance to fully rely on genomic information for selection decisions. Breeding objectives are highly dependent on the industry and the additional gain when using genomic information has to be considered carefully. This review synthesizes some of the suggested approaches in selected livestock species including cattle, pig, chicken, and fish. It outlines tasks to help understanding possible consequences when applying genomic information in breeding scenarios.

  18. Software qualification in safety applications

    International Nuclear Information System (INIS)

    Lawrence, J.D.

    2000-01-01

    The developers of safety-critical instrumentation and control systems must qualify the design of the components used, including the software in the embedded computer systems, in order to ensure that the component can be trusted to perform its safety function under the full range of operating conditions. There are well known ways to qualify analog systems using the facts that: (1) they are built from standard modules with known properties; (2) design documents are available and described in a well understood language; (3) the performance of the component is constrained by physics; and (4) physics models exist to predict the performance. These properties are not generally available for qualifying software, and one must fall back on extensive testing and qualification of the design process. Neither of these is completely satisfactory. The research reported here is exploring an alternative approach that is intended to permit qualification for an important subset of instrumentation software. The research goal is to determine if a combination of static analysis and limited testing can be used to qualify a class of simple, but practical, computer-based instrumentation components for safety application. These components are of roughly the complexity of a motion detector alarm controller. This goal is accomplished by identifying design constraints that enable meaningful analysis and testing. Once such design constraints are identified, digital systems can be designed to allow for analysis and testing, or existing systems may be tested for conformance to the design constraints as a first step in a qualification process. This will considerably reduce the cost and monetary risk involved in qualifying commercial components for safety-critical service

  19. Hybrid Qualifications Country report Denmark

    DEFF Research Database (Denmark)

    Jørgensen, Christian Helms

    2010-01-01

    The report explores the institutional and functional relations between the higher education (tertiary sector) and vocational education (higher secondary education) and the labour market. In the report are included descriptions of the history, funding, outcomes, institutional realisation and term ...... and range of hybrid qualifications in the national system. In addition some recommendations for constructive further developments are given.......The report explores the institutional and functional relations between the higher education (tertiary sector) and vocational education (higher secondary education) and the labour market. In the report are included descriptions of the history, funding, outcomes, institutional realisation and term...

  20. Appearance, discrimination, and reaction qualifications

    OpenAIRE

    Mason, Andrew

    2016-01-01

    When are selectors for advantaged social positions morally justified in giving weight to the appearance of the candidates? In order to address this issue adequately, we need to know when a person’s appearance can be a legitimate qualification for a position. Some of the hardest cases are jobs that involve interacting with clients or customers who prefer to deal with good-looking employees or who respond more favourably to them. But there is also a wide range of difficult cases in which an unc...

  1. Implications of NUREG-1150 for equipment qualification

    International Nuclear Information System (INIS)

    Siu, R.P.; Sarram, M.

    1988-01-01

    Current USNRC regulations in 10CFR50 requires that structures, systems and components important to safety in a nuclear power plant are to be designed to accommodate the effects of harsh environments associated with potential accidents. Detailed regulatory requirements are as discussed in Regulatory Guide 1.89. Some of these regulatory requirements have been based upon rather outdated understanding of the phenomenology of severe accidents -- e.g., the radiation source terms for equipment qualification can be traced to TID-14844 which was originally published in 1962. Furthermore, the definition of important-to-safety in these regulatory requirements is rather broad, usually resulting in a long Q-list of equipment to be qualified for the design-basis Large LOCA. In the past few years, extensive research/analysis on severe accidents have been conducted -- from the IREP/NREP activities, the IDCOR programs, to the NUREG-1150 efforts. This paper reports that as a result of all these PRA-related activities, a much-improved understanding of the phenomenology and environmental conditions associated with severe accidents has been gained

  2. Qualification criteria verification for aisi-4340 steel suspension lug

    International Nuclear Information System (INIS)

    Riaz, M.A.; Alam, M.

    2005-01-01

    All external loads carried underneath an aircraft are mounted onto it through mechanism generally known as suspension system. The externally mounted attachments like bombs, missiles and fuel tanks etc. experience enormous aerodynamic and inertial forces in the flights. These forces are transferred to the interface point of suspension system, known as 'Suspension Lug'. Thus lugs are considered critical component and have extremely stringent qualification criteria standards used in the aviation industry in USA, Europe, Russia, etc. Different standards prevail in different parts of the world about qualification and testing of these lugs. As Pakistan is entering into aviation industry, therefore there is a need to fulfill the requirements of these standards, to suit Pakistani environment. The suspension lug under study is 2000 Ibs. load class made from AISI-4340 Steel having good mechanical properties as per required standard. The manufacturing processes included forging, machining and vacuum heat treatment. The prototypes of suspension lugs were manufactured in the local industry and subjected to the required mechanical tests such as tensile testing at 5 to 35 degree angles. Impact testing at cryogenic temperatures of -50 to -70 degree C, and breaking load testing were performed. The acceptable results were obtained and mechanical testing for qualification of lugs was finalized and standardized. The options were compared with practical viability, utilization of product and cost effectiveness. (author)

  3. Manual on training, qualification and certification of quality assurance personnel

    International Nuclear Information System (INIS)

    1986-01-01

    The Manual is applicable to those participants in a nuclear power project who are associated with establishment and implementation of the various quality assurance (QA) programmes during the life cycle of the project. It provides examples of typical QA functions to be undertaken and the associated qualification requirements, training programmes, training techniques and methods of certification of personnel implementing these functions. The necessary qualification and training requirements and practices for QA personnel are dependent primarily on the functions or activities to be performed. The two main functions of the QA unit noted previously as (a) ensuring QA programme establishment and execution and (b) verifying that activities have been correctly performed have been found in practice to require different qualifications and training of personnel. Therefore, for the purpose of this Manual the QA personnel may be classified in two groups who perform: QA programmatic and evaluation functions; Inspection and test functions. These titles do not necessarily represent separate or individual organizational groups or units and may be composed of one or of several different organizations

  4. Qualification tests for a dosimetry system

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    The report of qualification tests for personnel dosemeters is detailed. Qualification test for the energy response and the incidence angle is given. The procedure of test is resumed. Different coefficients of conversion used in these tests are given in tables. (N.C.)

  5. 48 CFR 1553.209 - Contractor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Contractor qualifications. 1553.209 Section 1553.209 Federal Acquisition Regulations System ENVIRONMENTAL PROTECTION AGENCY CLAUSES AND FORMS FORMS Prescription of Forms 1553.209 Contractor qualifications. ...

  6. 48 CFR 253.209 - Contractor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Contractor qualifications. 253.209 Section 253.209 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE CLAUSES AND FORMS FORMS Prescription of Forms 253.209 Contractor qualifications. ...

  7. 48 CFR 53.209 - Contractor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Contractor qualifications. 53.209 Section 53.209 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS FORMS Prescription of Forms 53.209 Contractor qualifications. ...

  8. Qualification testing and electrical measurement experience: A manufacturer's view

    Science.gov (United States)

    Arnett, J. C.; Cooley, J. E.; Wingert, T. L.

    1983-11-01

    ARCO Solar's experiences as a participant in an industry-utility-government environmental qualification team examining photovoltaic devices are discussed. Included is an assessment of the applicability, completeness and appropriateness of the testing procedures and of the acceptance criteria for megawatt-sized procurements for utilities. Like the stand-alone users, the utility industry is interested in obtaining low costs, but additional concerns exist related to reliability and durability, safety, grounding and overall system criteria including performance prediction (related to output power acceptance testing), power quality and dispatchability. For purposes of this first major purchase of photovoltaic modules and panels by the utility industry, there was a carry-over of the JPL specifications. The need exists for futher development, assessement, and selection of qualification and testing standards and evaluation criteria specifically addressing these additional concerns for utility-connected PV power-plant applications.

  9. Methods Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Alessi, R. Sam; Grimmett, Tami; Vang, Leng; McGrath, Dave

    2010-01-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V and V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  10. Methods Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  11. Attentional Requirements for the Selection of Words from Different Grammatical Categories

    Science.gov (United States)

    Ayora, Pauline; Janssen, Niels; Dell'Acqua, Roberto; Alario, F.-Xavier

    2009-01-01

    Two grammatical classes are commonly distinguished in psycholinguistic research. The open-class includes content words such as nouns, whereas the closed-class includes function words such as determiners. A standing issue is to identify whether these words are retrieved through similar or distinct selection mechanisms. We report a comparative…

  12. Advanced qualification methodology for actively cooled plasma facing components

    Science.gov (United States)

    Durocher, A.; Escourbiac, F.; Grosman, A.; Boscary, J.; Merola, M.; Cismondi, F.; Courtois, X.; Farjon, J. L.; Missirlian, M.; Schlosser, J.; Tivey, R.

    2007-12-01

    The use of high heat flux plasma facing components (PFCs) in steady state fusion devices requires high reliability. These components have to withstand heat fluxes in the range 10-20 MW m-2 involving a number of severe engineering constraints. Feedback from the experience of various industrial manufacturings showed that the bonding of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on material qualities and specific design. As the heat exhaust capability and lifetime of PFCs during plasma operation are directly linked to the manufacturing quality, a set of qualification activities such as active infrared thermography, lock-in and acoustic measurements were performed during the component development phases following a qualification route. This paper describes the major improvements stemming from better measurement accuracy and refined data processing and analyses recent developments aimed at investigating the capability to qualify the component in situ during its lifetime.

  13. Advanced qualification methodology for actively cooled plasma facing components

    International Nuclear Information System (INIS)

    Durocher, A.; Escourbiac, F.; Grosman, A.; Boscary, J.; Merola, M.; Cismondi, F.; Courtois, X.; Farjon, J.L.; Missirlian, M.; Schlosser, J.; Tivey, R.

    2007-01-01

    The use of high heat flux plasma facing components (PFCs) in steady state fusion devices requires high reliability. These components have to withstand heat fluxes in the range 10-20 MW m -2 involving a number of severe engineering constraints. Feedback from the experience of various industrial manufacturings showed that the bonding of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on material qualities and specific design. As the heat exhaust capability and lifetime of PFCs during plasma operation are directly linked to the manufacturing quality, a set of qualification activities such as active infrared thermography, lock-in and acoustic measurements were performed during the component development phases following a qualification route. This paper describes the major improvements stemming from better measurement accuracy and refined data processing and analyses recent developments aimed at investigating the capability to qualify the component in situ during its lifetime

  14. Accreditation of qualification testing organizations: the industry viewpoint

    International Nuclear Information System (INIS)

    Roby, A.

    1983-01-01

    This paper presents the industry viewpoint on the program for the Accreditation of Qualification Testing Organizations, which has been proposed for rulemaking by the Nuclear Regulatory Commission. The IEEE has agreed to establish the program content, and would administer its requirements in accordance with an agreement between the NRC and IEEE of September 30th, 1981. Presented in this paper is the industry perspective, developed and prepared through the AIF, identifying the serious concerns which the accreditation program has raised. Discussed are the disadvantages of the program and those present benefits which would be lost if the program was adopted. The value of greater emphasis on current regulation to improve the qualification process is presented and the paper details areas where the NRC proposals do not provide adequate justification for the accreditation program

  15. ITER tungsten divertor design development and qualification program

    Energy Technology Data Exchange (ETDEWEB)

    Hirai, T., E-mail: takeshi.hirai@iter.org [ITER Organization, Route de Vinon sur Verdon, F-13115 Saint Paul lez Durance (France); Escourbiac, F.; Carpentier-Chouchana, S.; Fedosov, A.; Ferrand, L.; Jokinen, T.; Komarov, V.; Kukushkin, A.; Merola, M.; Mitteau, R.; Pitts, R.A.; Shu, W.; Sugihara, M. [ITER Organization, Route de Vinon sur Verdon, F-13115 Saint Paul lez Durance (France); Riccardi, B. [F4E, c/ Josep Pla, n.2, Torres Diagonal Litoral, Edificio B3, E-08019 Barcelona (Spain); Suzuki, S. [JAEA, Fusion Research and Development Directorate JAEA, 801-1 Mukouyama, Naka, Ibaragi 311-0193 (Japan); Villari, R. [Associazione EURATOM-ENEA sulla Fusione, Via Enrico Fermi 45, I-00044 Frascati, Rome (Italy)

    2013-10-15

    Highlights: • Detailed design development plan for the ITER tungsten divertor. • Latest status of the ITER tungsten divertor design. • Brief overview of qualification program for the ITER tungsten divertor and status of R and D activity. -- Abstract: In November 2011, the ITER Council has endorsed the recommendation that a period of up to 2 years be set to develop a full-tungsten divertor design and accelerate technology qualification in view of a possible decision to start operation with a divertor having a full-tungsten plasma-facing surface. To ensure a solid foundation for such a decision, a full tungsten divertor design, together with a demonstration of the necessary high performance tungsten monoblock technology should be completed within the required timescale. The status of both the design and technology R and D activity is summarized in this paper.

  16. Initial qualifications of adult educators – a comparative view

    DEFF Research Database (Denmark)

    Milana, Marcella; Larson, Anne; Søgaard Lund, Lise

    General adult education, vocationally oriented adult education and liberal education often represent separated fields of public intervention. Each of these sectors is characterized by organizational features and a financial structure that support the pursuing of specific educational goals....... These distinctions are reflected not only in the provision of adult education opportunities but also in public policies on adult learning. Consequently, initial education and training of adult educators as well as the policy on qualification of adult education professionals differs both between countries and between......, the paper will critically review current public policies in the field and problematise the role of existing education and training opportunities in providing those willing to teach adults in general adult education, vocationally oriented adult education or liberal education with the qualifications required...

  17. Developments in mechanical ultrasonic inspection and qualification of NDE

    International Nuclear Information System (INIS)

    Kauppinen, P.; Pitkaenen, J.; Kuusinen, P.

    2001-01-01

    Reliability of non-destructive testing results has a direct influence on structural integrity assessment and safety of the inspected structures e.g. NPP primary circuit pressure boundaries. Advanced technology together with highly skilled and experienced personnel is required. One of the current trends is automation. Mechanised equipment can replace tedious manual work in positioning and moving of the transducers. Large areas can be scanned, analysed and numerically documented for direct comparison of eventual later repeated inspections. Another major trend is qualification, which aims to ensure that the inspection results are correct and fit the purpose. The suitability and proper operation of equipment, methods and personnel i.e. the whole chain shall be proven. This presentation summarises the advances in automation and qualification of non-destructive inspection during the second project year, Monitoring of material degradation was included in the studied topics and will also be shortly described. (author)

  18. Environmental qualification test of electrical penetration for nuclear power stations

    International Nuclear Information System (INIS)

    Kooziro, Tetsuya; Nakagawa, Akitoshi; Toyoda, Shigeru; Uno, Shunpei

    1979-01-01

    Environmental qualification test was conducted according to IEEE Std. 323-1974 in order to evaluate the safety and reliability of electrical penetration of PWR type nuclear power station. Electrical penetration is the assemblies of electric cables attached to the containment vessel and penetrate through the vessel. Since it is a part of the vessel, it is deemed to be one of the primary safety equipments that are important for the safety and reliability of nuclear power stations. Environmental tests were conducted continuously as to heat cycle, vibration and LOCA with the full size specimens of bushing type, pigtail type and triaxial cable type and at the same time thermal life and irradiation tests were conducted on the insulation materials used, in order to obtain the comprehensive evaluation of their electrical and mechanical characteristics. As the result, they all satisfied the requirements for the circuits for actual use during and after various environmental qualification tests according to IEEE Std. 323. (author)

  19. The qualification of electrical components and instrumentations relevant to safety

    CERN Document Server

    Zambardi, F

    1989-01-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and ...

  20. Quality assurance program preparation - review of requirements and plant systems - selection of program levels

    International Nuclear Information System (INIS)

    Asmuss, G.

    1980-01-01

    The establishment and implementation for a practicable quality assurance program for a nuclear power plant demands a detailed background in the field of engineering, manufacturing, organization and quality assurance. It will be demonstrated with examples to define and control the achievement of quality related activities during the phases of design, procurement, manufactoring, commissioning and operation. In general the quality assurance program applies to all items, processes and services important to safety of nuclear power plant. The classification for safety related and non-safety related items and services demonstrate the levels of quality assurance requirements. The lecture gives an introduction of QA Program preparation under the following topics: -Basic criteria and international requirements - Interaction of QA activities - Modular and product oriented QA programs - Structuring of organization for the QA program - Identification of the main quality assurance functions and required actions - Quality Assurance Program documentation - Documentation of planning of activities - Control of program documents - Definitions. (orig./RW)

  1. The Training Requirements of the Clothing Industry. A Survey of Selected Occupations.

    Science.gov (United States)

    Berry, Kathleen M.; Kuhl, Dean H.

    This survey was conducted in order to determine the training requirements of the clothing industry in South Australia. The results and findings are intended to be used as a means for upgrading and revising the Clothing Production Certificate Course and for providing suitable training programs for other key occupations within the industry. Survey…

  2. Review of selected contributions of the conference 'Suppliers and requirements for quality provision'

    International Nuclear Information System (INIS)

    2007-03-01

    There were 12 contributions presented at the conference focused on the requirements of the standard ISO 9001:2000 for supplies of services and products, especially from the point of view of supplies for nuclear power plants. Two contributions were focused in the issue of quality assurance of finishing of the building of 3. and 4. block of the Nuclear Power Plant Mochovce

  3. AGC-3 Experiment Irradiation Monitoring Data Qualification Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Hull, Laurence C. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Technology Development Office

    2014-08-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear-grade graphite. The third experiment, Advanced Graphite Creep 3 (AGC-3), began with Advanced Test Reactor (ATR) Cycle 152B on November 27, 2012, and ended with ATR Cycle 155B on April 23, 2014. This report documents qualification of AGC-3 experiment irradiation monitoring data for use by the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Program for research and development activities required to design and license the first VHTR nuclear plant. Qualified data meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Failed data do not meet the requirements. Trend data may not meet the requirements, but may still provide some useable information. The report documents qualification of AGC-3 experiment irradiation monitoring data following MCP-2691. This report also documents whether AGC-3 experiment irradiation monitoring data meet the requirements for data collection as specified in technical and functional requirements documents and quality assurance (QA) plans. Data handling is described showing how data are passed from the data collection experiment to the Nuclear Data Management and Analysis System (NDMAS) team. The data structure is described, including data batches, components, attributes, and response variables. The description of the approach to data qualification includes the steps taken to qualify the data and the specific tests used to verify that the data meet requirements. Finally, the current status of the data received by NDMAS from the AGC-3 experiment is presented with summarized information on test results and resolutions. This report addresses all of the irradiation monitoring data collected during the AGC-3 experiment.

  4. Similarity principles for equipment qualification by experience

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1988-07-01

    A methodology is developed for seismic qualification of nuclear plant equipment by applying similarity principles to existing experience data. Experience data are available from previous qualifications by analysis or testing, or from actual earthquake events. Similarity principles are defined in terms of excitation, equipment physical characteristics, and equipment response. Physical similarity is further defined in terms of a critical transfer function for response at a location on a primary structure, whose response can be assumed directly related to ultimate fragility of the item under elevated levels of excitation. Procedures are developed for combining experience data into composite specifications for qualification of equipment that can be shown to be physically similar to the reference equipment. Other procedures are developed for extending qualifications beyond the original specifications under certain conditions. Some examples for application of the procedures and verification of them are given for certain cases that can be approximated by a two degree of freedom simple primary/secondary system. Other examples are based on use of actual test data available from previous qualifications. Relationships of the developments with other previously-published methods are discussed. The developments are intended to elaborate on the rather broad revised guidelines developed by the IEEE 344 Standards Committee for equipment qualification in new nuclear plants. However, the results also contribute to filling a gap that exists between the IEEE 344 methodology and that previously developed by the Seismic Qualification Utilities Group. The relationship of the results to safety margin methodology is also discussed. (author)

  5. 49 CFR 180.507 - Qualification of tank cars.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Qualification of tank cars. 180.507 Section 180... QUALIFICATION AND MAINTENANCE OF PACKAGINGS Qualification and Maintenance of Tank Cars § 180.507 Qualification of tank cars. (a) Each tank car marked as meeting a “DOT” specification or any other tank car used...

  6. WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

    Energy Technology Data Exchange (ETDEWEB)

    Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Hanford Missions Programs; Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Process Technology Programs; Johnson, F. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development; Edwards, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development

    2016-07-14

    The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the process demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the

  7. Training and qualification of inspectors

    International Nuclear Information System (INIS)

    Aro, I.; Anderson, R.; Ericsson, P.O.; Lee, I.

    1993-01-01

    A total of four workshop breakout sessions were conducted on this subject: one double session and three single sessions. The following discussion describes common points and difference among the countries in the areas of inspector training and qualifications. In most countries there are resident or non-resident site-specific inspectors who have general plant supervision duties. In addition, there are specialized inspectors who visit NPP when requested or according to the scheduled inspection program. Most countries try to recruit experienced personnel. Many countries prefer to have candidates who have extensive plant experience. Some countries do not recruit inspectors from utilities because of potential conflict of interest or credibility reasons. In many countries, the typical training time to become an independent inspector is one year. In some countries an inspector is formally certified after their training period and completion of an examination

  8. VHDL basics applied design by SIPAC qualification system

    International Nuclear Information System (INIS)

    Park, In Ha; Mun, Da Cheol; Lee, Gwang Yeob

    2005-12-01

    This book has six chapters, which are about Flowrian of SIPAC qualification system including internet CAD system and remote server service, logic circuit on design and qualification of device such as gate circuit, multiplex and decoder, order logic circuit with D type flip-flop design and qualification and Rom and RAM's design and qualification, finite state machine such as odd checker, sequence detector, test clock generator and traffic light controller, design and qualification about data path, design of application circuit. It has two appendixes on install and the way to use SIPAC qualification system and remote service for SIPAC qualification system.

  9. Environmental qualification testing of TFE valve components

    International Nuclear Information System (INIS)

    Eyvindson, A.; Krasinski, W.; McCutcheon, R.

    1997-01-01

    Valves containing tetrafluoroethylene (TFE) components are being used in many CANDU Nuclear Generating Stations. However, some concerns remain about the performance of TFE after exposure to high levels of radiation. Stations must therefore ensure that such valves perform reliably after being exposed to postulated accident radiation dose levels. The current Ontario Hydro Environmental Qualification [EQ] program specifies much higher postulated radiation exposure than the original design, to account for conditions following a LOCA. Initial assessments indicated that Teflon components would require replacement. Proof of acceptable performance can remove the need for large scale replacement, avoiding a significant cost penalty and preserving benefits due to the superior performance of TFE-based seals. A test program was undertaken at Chalk River Laboratories (CRL) to investigate the performance of three valves after irradiation to 10 Mrad. Such valves are currently used at the Bruce B Nuclear Generating Station. Each contains TFE packing rings; one also has TFE seats. Two of the valves are used in the ECIS recovery system, while the third is used for instrumentation loop isolation or as drain valves. All are exposed to little or no radiation during normal use. Based on the results of the tests, all the valves tested will still meet functional and performance requirements after the TFE components have been exposed to 10 Mrad of irradiation. (author)

  10. Workshop on environmental qualification of electric equipment

    International Nuclear Information System (INIS)

    Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J.

    1994-05-01

    Questions concerning the Environmental Qualification (EQ) of electrical equipment used in commercial nuclear power plants have recently become the subject of significant interest to the US Nuclear Regulatory Commission (NRC). Initial questions centered on whether compliance with the EQ requirements for older plants were adequate to support plant operation beyond 40 years. After subsequent investigation, the NRC Staff concluded that questions related to the differences in EQ requirements between older and newer plants constitute a potential generic issue which should be evaluated for backfit, independent of license renewal activities. EQ testing of electric cables was performed by Sandia National Laboratories (SNL) under contract to the NRC in support of license renewal activities. Results showed that some of the environmentally qualified cables either failed or exhibited marginal insulation resistance after a simulated plant life of 20 years during accident simulation. This indicated that the EQ process for some electric cables may be non-conservative. These results raised questions regarding the EQ process including the bases for conclusions about the qualified life of components based upon artificial aging prior to testing

  11. Workshop on environmental qualification of electric equipment

    Energy Technology Data Exchange (ETDEWEB)

    Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J. [comps.] [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01

    Questions concerning the Environmental Qualification (EQ) of electrical equipment used in commercial nuclear power plants have recently become the subject of significant interest to the US Nuclear Regulatory Commission (NRC). Initial questions centered on whether compliance with the EQ requirements for older plants were adequate to support plant operation beyond 40 years. After subsequent investigation, the NRC Staff concluded that questions related to the differences in EQ requirements between older and newer plants constitute a potential generic issue which should be evaluated for backfit, independent of license renewal activities. EQ testing of electric cables was performed by Sandia National Laboratories (SNL) under contract to the NRC in support of license renewal activities. Results showed that some of the environmentally qualified cables either failed or exhibited marginal insulation resistance after a simulated plant life of 20 years during accident simulation. This indicated that the EQ process for some electric cables may be non-conservative. These results raised questions regarding the EQ process including the bases for conclusions about the qualified life of components based upon artificial aging prior to testing.

  12. An analysis of the qualification criteria for small radioactive material shipping packages

    Energy Technology Data Exchange (ETDEWEB)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

  13. An analysis of the qualification criteria for small radioactive material shipping packages

    International Nuclear Information System (INIS)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described

  14. Fiber Laser Component Testing for Space Qualification Protocol Development

    Science.gov (United States)

    Falvey, S.; Buelow, M.; Nelson, B.; Starcher, Y.; Thienel, L.; Rhodes, C.; Tull, Jackson; Drape, T.; Westfall, C.

    A test protocol for the space qualifying of Ytterbium-doped diode-pumped fiber laser (DPFL) components was developed under the Bright Light effort, sponsored by AFRL/VSE. A literature search was performed and summarized in an AMOS 2005 conference paper that formed the building blocks for the development of the test protocol. The test protocol was developed from the experience of the Bright Light team, the information in the literature search, and the results of a study of the Telcordia standards. Based on this protocol developed, test procedures and acceptance criteria for a series of vibration, thermal/vacuum, and radiation exposure tests were developed for selected fiber laser components. Northrop Grumman led the effort in vibration and thermal testing of these components at the Aerospace Engineering Facility on Kirtland Air Force Base, NM. The results of the tests conducted have been evaluated. This paper discusses the vibration and thermal testing that was executed to validate the test protocol. The lessons learned will aid in future assessments and definition of space qualification protocols. Components representative of major items within a Ytterbium-doped diode-pumped fiber laser were selected for testing; including fibers, isolators, combiners, fiber Bragg gratings, and laser diodes. Selection of the components was based on guidelines to test multiple models of typical fiber laser components. A goal of the effort was to test two models (i.e. different manufacturers) of each type of article selected, representing different technologies for the same type of device. The test articles did not include subsystems or systems. These components and parts may not be available commercial-off-the-shelf (COTS), and, in fact, many are custom articles, or newly developed by the manufacturer. The primary goal for this effort is a completed taxonomy that lists all relevant laser components, modules, subsystems, and interfaces, and cites the documentation for space

  15. Equipment Qualification Data Base user manual

    International Nuclear Information System (INIS)

    Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

    1985-09-01

    This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

  16. Solar array qualification through qualified analysis

    Science.gov (United States)

    Zijdemans, J.; Cruijssen, H. J.; Wijker, J. J.

    1991-04-01

    To achieve qualification is in general a very expensive exercise. For solar arrays this is done by a dedicated test program through which final qualification is achieved. Due to severe competition on the solar array market, cheaper means are looked for to achieve a qualified product for the customers. One of the methods is to drastically limit the environmental test program and to qualify the solar-array structure against its environmental loads by analysis. Qualification by analysis is possible. The benefits are that a significant amount of development effort can be saved in case such a powerful tool is available. Extensive testing can be avoided thus saving time and money.

  17. QUALIFICATIONS FRAMEWORK DEVELOPMENT AND QUALIFICATIONS RATING IN THE LAND MANAGEMENT SPHERE

    Directory of Open Access Journals (Sweden)

    A. A. Myrasheva

    2014-01-01

    Full Text Available The aim of the research is to observe the existing approaches to qualifications framework development in the sphere of land management, cadastres and real estate management, as well as the qualifications framework adaptation to European system. The relevance of the issue is related to the specific professional and institutional problems facing Russian educational establishments engaged in personnel training in the given sphere. The authors demonstrate the qualifications framework development in the land management sector regarding it as a key mechanism of educational mobility and the router for knowledge acquisition and updates. The qualifications framework is referred to as a systematic and structured description of recognized qualifications. The accepted worldwide methodology of organizing the educational process and quality control system is given. The emphasis is on the need to comply the qualifications framework with the Russian State Educational Standards.

  18. Towards harmonized qualifications for radiation exposed personnel

    International Nuclear Information System (INIS)

    Briso, Hugo A.

    2008-01-01

    requirements due to the universe of radiation exposed personnel diversifying their specialization by areas, i.e. medical, industrial and research, as much in normal operation as in emergency situations. It also seeks to allow common approaches to enable the educational institutions as well as to assess the qualifications of operator applicants. (author)

  19. SELECTED REQUIREMENTS OF INTEGRATED MANAGEMENT SYSTEMS BASED ON PAS 99 SPECIFICATION

    Directory of Open Access Journals (Sweden)

    Paweł Nowicki

    2013-03-01

    Full Text Available The aim this research was to analyze the ways of integration of management systems in food sector. The study involved the documentation, audits, corrective and preventive actions and management's review phases described in the specification PAS 99, which is one of common elements of integrated management systems. Four organizations were selected for the study. The organizations had introduced and certified at least two standardized management systems. It was assumed that the investigated organizations should have implemented the HACCP system. Studies were conducted as a case study. The employees responsible for the functioning of management systems were interviewed in all four organizations. The study was conducted in the form of in-depth interviews based on pre-prepared script. The scenario was developed based on the PAS 99 guideline. The process of integration of management systems implemented in the studied companies reveals the full compliance of an integrated management system with PASS 99 in the policy area.

  20. Striatal fast-spiking interneurons selectively modulate circuit output and are required for habitual behavior.

    Science.gov (United States)

    O'Hare, Justin K; Li, Haofang; Kim, Namsoo; Gaidis, Erin; Ade, Kristen; Beck, Jeff; Yin, Henry; Calakos, Nicole

    2017-09-05

    Habit formation is a behavioral adaptation that automates routine actions. Habitual behavior correlates with broad reconfigurations of dorsolateral striatal (DLS) circuit properties that increase gain and shift pathway timing. The mechanism(s) for these circuit adaptations are unknown and could be responsible for habitual behavior. Here we find that a single class of interneuron, fast-spiking interneurons (FSIs), modulates all of these habit-predictive properties. Consistent with a role in habits, FSIs are more excitable in habitual mice compared to goal-directed and acute chemogenetic inhibition of FSIs in DLS prevents the expression of habitual lever pressing. In vivo recordings further reveal a previously unappreciated selective modulation of SPNs based on their firing patterns; FSIs inhibit most SPNs but paradoxically promote the activity of a subset displaying high fractions of gamma-frequency spiking. These results establish a microcircuit mechanism for habits and provide a new example of how interneurons mediate experience-dependent behavior.

  1. Qualification of C and I systems using new technology components

    International Nuclear Information System (INIS)

    Gossner, S.

    1986-01-01

    Whereas one may find an almost complete change-over to microprocessor based automation and supervision systems in numerous industrial fields, a similar development did not yet take place in C and I systems of West German nuclear power plants. Neglecting some unimportant exceptions C and I systems of West German nuclear power plants are fully conventional. This situation, however, will not last forever. There is a growing understanding that by means of microcomputer-based C and I equipment it will be possible: to solve many problems more exactly, e.g. calculations of reactor power, power distribution, water levels, DNBR; to reduce the number of detailed informations and alarms concentrated in control rooms and control stations and to condense these informations into easily to understand pictorial displays, e.g. surveillance or trend pictures on graphic CRT-display units; to reduce cabling amount by using sequential data transmission, e.g. by means of bus-systems. It's clear in the near future microprocessors will enter not only operational C and I equipment but C and I systems important to safety as well. Therefore it's high time to analyse existing design and qualification requirements, qualification methods and qualification procedures whether or not to be suitable and sufficient

  2. Seismic and environmental qualification of class IE equipment manufactured in Spain

    International Nuclear Information System (INIS)

    Gerini, P.; Lumbreras, A.; Naredo, F.

    1978-01-01

    Nuclear power plant instrumentation and control design is affected by several factors such as various plant operating conditions, transient response capability, safety requirements and changes in IEEE standards. Recent upgraded IEEE standards that call for Qualification of all Safety related I anc C equipment, namely IEEE 323 (Qualifying Class IE Electric Equipment for nuclear power generating stations) and its daughter Standard IEEE 344 (Recommended Practices for Seismic Qualification of Class IE Equipment for nuclear power generating stations) have been endorsed by the United States Nuclear Regulatory Commission through the issuance of corresponding Regulatory Guides. The author describes the Qualification requirements applicable to the Class IE I and C Components made in Spain for the different vintages of plants, and the programs implemented or plans established by Westinghouse to fulfill those requirements. (author)

  3. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    Energy Technology Data Exchange (ETDEWEB)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  4. Visas and qualifications: Syrian refugees in Brazil

    Directory of Open Access Journals (Sweden)

    Gilberto M A Rodrigues

    2017-10-01

    Full Text Available Brazil’s humanitarian visa programme for Syrian refugees and its efforts to recognise their qualifications could offer lessons for refugee protection and integration across the region.

  5. Qualification of anticorrosive coatings in nuclear vessels

    International Nuclear Information System (INIS)

    Perez Flores, C.

    1985-01-01

    Test qualifications of the behavior of anticorrosive coating systems used in nuclear vessels in service and under the accident conditions of radiation decontamination, steam chemical resistance, thermal conductivity, weathering accelerated aging are presented and discussed. (author)

  6. Qualification and testing of CT systems

    DEFF Research Database (Denmark)

    Bartscher, Markus; Neuschaefer-Rube, Ulrich; Illemann, Jens

    2018-01-01

    This chapter focuses on system verification and conformance to specifications. System qualification is carried out to ensure that the system and itscomponents achieve the best performance—usually corresponding to the specificationsmade by the manufacturer. Acceptance and reverification testing ar...

  7. Selected issues connected with determination of requirements of spectral properties of camouflage patterns

    Science.gov (United States)

    Racek, František; Jobánek, Adam; Baláž, Teodor; Krejčí, Jaroslav

    2017-10-01

    Traditionally spectral reflectance of the material is measured and compared with permitted spectral reflectance boundaries. The boundaries are limited by upper and lower curve of spectral reflectance. The boundaries for unique color has to fulfil the operational requirements as a versatility of utilization through the all year seasons, day and weather condition on one hand and chromatic and spectral matching with background as well as the manufacturability on the other hand. The interval between the boundaries suffers with ambivalent feature. Camouflage pattern producer would be happy to see it much wider, but blending effect into its particular background could be better with narrower tolerance limits. From the point of view of long time user of camouflage pattern battledress, there seems to be another ambivalent feature. Width of the tolerance zone reflecting natural dispersion of spectral reflectance values allows the significant distortions of shape of the spectral curve inside the given boundaries.

  8. Assessing mathematics within advanced school science qualifications

    OpenAIRE

    McAlinden, Mary; Noyes, Andrew

    2017-01-01

    Following sustained discussion regarding the relationship between advanced mathematics and science learning in England, the government has pursued a reform agenda in which mathematics is embedded in national, high stakes A-level science qualifications and their assessments for 18-year-olds. For example, A-level Chemistry must incorporate the assessment of relevant mathematics for at least 20% of the qualification. Other sciences have different mandated percentages. This embedding policy is ru...

  9. Selective transcription and cellular proliferation induced by PDGF require histone deacetylase activity

    International Nuclear Information System (INIS)

    Catania, Annunziata; Iavarone, Carlo; Carlomagno, Stella M.; Chiariello, Mario

    2006-01-01

    Histone deacetylases (HDACs) are key regulatory enzymes involved in the control of gene expression and their inhibition by specific drugs has been widely correlated to cell cycle arrest, terminal differentiation, and apoptosis. Here, we investigated whether HDAC activity was required for PDGF-dependent signal transduction and cellular proliferation. Exposure of PDGF-stimulated NIH3T3 fibroblasts to the HDAC inhibitor trichostatin A (TSA) potently repressed the expression of a group of genes correlated to PDGF-dependent cellular growth and pro-survival activity. Moreover, we show that TSA interfered with STAT3-dependent transcriptional activity induced by PDGF. Still, neither phosphorylation nor nuclear translocation and DNA-binding in vitro and in vivo of STAT3 were affected by using TSA to interfere with PDGF stimulation. Finally, TSA treatment resulted in the suppression of PDGF-dependent cellular proliferation without affecting cellular survival of NIH3T3 cells. Our data indicate that inhibition of HDAC activity antagonizes the mitogenic effect of PDGF, suggesting that these drugs may specifically act on the expression of STAT-dependent, PDGF-responsive genes

  10. Report on data requirements and hardware selection for in-situ ball viscometer

    International Nuclear Information System (INIS)

    Shepard, C.L.

    1994-12-01

    The in-situ ball rheometer is designed to provide data concerning the rheological properties of the waste contained in tank 101-SY. It is imperative that the data collected and the results obtained are useful to the community presently concerned with the mitigation of the waste contained within this tank. To ensure that this objective is met, discussions were held with representatives of different groups in order to determine their data needs. This report is a synopsis of these discussions. Four separate groups were identified as potential users of the data. Persons contacted included Don Trent (Pacific Northwest Laboratory (PNL)), who is involved with Tempest modeling of the tank; Randy Marlow and John Strehlow (Westinghouse Hanford Company (WHC)), involved with structural analysis of the tank; Kemal Pasamehmetoglu and Cetin Unal (Los Alamos National Laboratory (LANL)), who are concerned with the safety analysis of activities performed within the tank; and Judith Bamberger, Paul Scott, and Gita Golcar (PNL) who are involved with the eventual retrieval of waste from the tank. Very specific questions were asked of these groups, including: From where in the tank are data needed? When should data be collected? In what manner are the data useful? What is the required accuracy of the data? Responses from each group are given

  11. On tungsten technologies and qualification for DEMO

    International Nuclear Information System (INIS)

    Laan, J. van der; Hegeman, H.; Wouters, O.; Luzginova, N.; Jonker, B.; Van der Marck, S.; Opschoor, J.; Wang, J.; Dowling, G.; Stuivenga, M.; Carton, E.

    2009-01-01

    Tungsten alloys are considered prime candidates for the in-vessel components directly facing the plasma. For example, in the HEMJ helium cooled divertor design tiles may be operated at temperatures up to 1700 deg. C, supported by a structure partially consisting of tungsten at temperatures from 600 to 1000 deg. C, and connected to a HT steel structure. The tungsten armoured primary wall is operated at 500-900 deg. C. Irradiation doses will be few tens dpa at minimum, but FPR requirements for plants availability will stretch these targets. Recently injection moulding technology was developed for pure tungsten and representative parts were manufactured for ITER monobloc divertors and DEMO HEMJ thimbles. The major advantages for this technology are the efficient use of material feedstock/resources and the intrinsic possibility to produce near-finished product, avoiding machining processes that are costly and may introduce surface defects deteriorating the component in service performance. It is well suited for mass-manufacturing of components as well known in e.g. lighting industries. To further qualify this material technology various specimen types were produced with processing parameters identical to the components, and tested successfully, showing the high potential for implementation in (fusion) devices. Furthermore, the engineering approach can clearly be tailored away from conventional design and manufacturing technologies based on bulk materials. The technology is suitable for shaping of new W-alloys and W-ODS variants as well. Basically this technology allows a particular qualification trajectory. There is no need to produce large batches of material during the material development and optimization stage. For the verification of irradiation behaviour in the specific neutron spectra, there is a further attractive feature to use e.g. isotope tailored powders to adjust to available irradiation facilities like MTR's. In addition the ingrowth of transmutation

  12. Philosophy, qualifications and training in Canada

    International Nuclear Information System (INIS)

    Rheaume, R.

    1989-01-01

    The Canadian nuclear power industry record concerning radiation protection is commendable, with low doses and no over-exposures, and this despite the much higher risk in this sector compared with the other sectors studied. Various technical factors have contributed towards this achievement, of course, but the philosophy adopted and the high level of qualification of the radiation protection personnel have played a major role. A great deal of work has been put into training nuclear plant operatives up to the desired level, since many were not particularly well-educated. The solution has been to improve the teaching aspect of the training, and to clearly identify the workers' needs by analyzing the tasks which they are required to perform. Consequently, the creation of a systematic training programme for users of radiation sources in universities and hospitals would help to improve radiation protection, especially as the users in this sector are generally better educated than the maintenance workers in power stations. In the mining sector, training does not have such a significant role to play in dose reduction, but it will nevertheless have an indirect impact: once miners know more about radiation and its health implications, their demands, on issues such as ventilation, for example, will become more specific and have more substance

  13. Orifice jet brazing process development, qualification, and initial application

    International Nuclear Information System (INIS)

    1971-05-01

    Experiments were carried out to develop acceptable procedures for brazing molybdenum alloy orifices to fuel element channel inlets of the NERVA R-1 reactor core. Results achieved with various procedures are described, and qualification tests of the selected process are documented. The recommended procedure includes preplacing of Au-Ni-Cr alloy washers and induction heating to 1600 0 F, holding two minutes, heating further to 2400 0 F, holding one minute, and allowing to cool. Inert atmosphere is used, and fixturing maintains proper positioning of the orifices. Leak testing of the joints has demonstrated reproducibly satisfactory sealing. Repair brazing is feasible if needed. (auth)

  14. Implementation and Qualifications Lessons Learned for Space Flight Photonic Components

    Science.gov (United States)

    Ott, Melanie N.

    2010-01-01

    This slide presentation reviews the process for implementation and qualification of space flight photonic components. It discusses the causes for most common anomalies for the space flight components, design compatibility, a specific failure analysis of optical fiber that occurred in a cable in 1999-2000, and another ExPCA connector anomaly involving pins that broke off. It reviews issues around material selection, quality processes and documentation, and current projects that the Photonics group is involved in. The importance of good documentation is stressed.

  15. Training, education and qualification of NPP operating personnel in the Netherlands

    International Nuclear Information System (INIS)

    de Vrey, G.A.

    1987-01-01

    This paper outlines the organization and the requirements of the training, education and qualification of NPP operating personnel in the Netherlands. It describes the implementation of a formally required scheme of personnel qualification after TMI, and the current practice as developed by the training staff of both Dutch nuclear power plants. Attention is given to the specific circumstances and problems in the Netherlands, and the resulting program. The licensing criteria for control room operating personnel are discussed, including the level of government involvement. Measures are described to improve the approach to training of NPP personnel involved in safety relevant activities. Finally, some ideas are given for strategies to cope with adverse stress situations

  16. Decree of the President of the Republic No. 1450 of 30 December 1970. Regulations concerning the recognition of the qualifications for technical operation of nuclear installations

    International Nuclear Information System (INIS)

    1971-01-01

    This Decree made in implementation of Act No. 1860 establishes the requirements and the procedure for obtaining the qualifications necessary for the technical management of nuclear installations. It also determines the classes of installations connected with each type of qualification. (NEA) [fr

  17. Neutron absorber qualification and acceptance testing from the designer's perspective

    International Nuclear Information System (INIS)

    Bracey, W.; Chiocca, R.

    2004-01-01

    Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3σ. The original and current bases for the reduced 10 B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and process controls

  18. Qualification of Daiichi Units 1, 2, and 3 Data for Severe Accident Evaluations - Process and Illustrative Examples from Prior TMI-2 Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Rempe, Joy Lynn [Idaho National Lab. (INL), Idaho Falls, ID (United States); Knudson, Darrell Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This initial review focused on the set of sensors deemed most important by post-TMI-2 instrumentation evaluation programs. Instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. In addition, prior efforts focused on sensors providing data required for subsequent forensic evaluations and accident simulations. To encourage the potential for similar activities to be completed for qualifying data from Daiichi Units 1, 2, and 3, this report provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: primary system pressure; containment building temperature; and containment pressure. As described within this report, sensor evaluations and data qualification required implementation of various processes, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design to instruments easily removed from the TMI-2 plant for evaluations. As documented

  19. Qualification test for ITER HCCR-TBS mockups with high heat flux test facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Suk-Kwon, E-mail: skkim93@kaeri.re.kr [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Seong Dae; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae-Sung; Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

    2016-11-01

    Highlights: • The test mockups for ITER HCCR (Helium Cooled Ceramic Reflector) TBS (Test Blanket System) in Korea were designed and fabricated. • A thermo-hydraulic analysis was performed using a high heat flux test facility by using electron beam. • The plan for qualification tests was developed to evaluate the thermo-hydraulic efficiency in accordance with the requirements of the ITER Organization. - Abstract: The test mockups for ITER HCCR (Helium Cooled Ceramic Reflector) TBS (Test Blanket System) in Korea were designed and fabricated, and an integrity and thermo-hydraulic performance test should be completed under the same or similar operation conditions of ITER. The test plan for a thermo-hydraulic analysis was developed by using a high heat flux test facility, called the Korean heat load test facility by using electron beam (KoHLT-EB). This facility is utilized for a qualification test of the plasma facing component (PFC) for the ITER first wall and DEMO divertor, and for the thermo-hydraulic experiments. In this work, KoHLT-EB will be used for the plan of the performance qualification test of the ITER HCCR-TBS mockups. This qualification tests should be performed to evaluate the thermo-hydraulic efficiency in accordance with the requirements of the ITER Organization (IO), which describe the specifications and qualifications of the heat flux test facility and test procedure for ITER PFC.

  20. Generic test procedure for the qualification of a nuclear emergency generator

    International Nuclear Information System (INIS)

    Simonis, J.C.; Bowman, S.W.

    1985-01-01

    This paper describes the proposed analytical and experimental procedures for the qualification of the standby generators and exciters used in the Emergency Diesel Generator Systems in a nuclear power plant. The components which require qualification are identified through a failure mode analysis of the systems conducted using engineering drawings updated to include all field changes. The qualification of each component includes the margins given in IEEE Std. 323-1974, ''Qualifying Class 1E Equipment for Nuclear Power Generating Stations.'' These margins are combined with the plant specific data to define an enveloping set of environmental parameters. This set of enveloping parameters, plus margin, form the bases for the analysis or test qualification tasks. Proposed qualification of the composite electrical insulation systems used in the generator and exciter on the form or random wound coils is by traceable testing. However, before testing the thermal and radiation degradation data used in the design of the generator and exciter are evaluated to identify if these data are sufficiently traceable to eliminate the need for additional insulation tests. The required tests are guided by applicable standards

  1. Qualification Needs, Approaches and Strategies in the Second-Hand Sector. A European Good-Practice Report

    OpenAIRE

    Arold, Heike; Koring, Claudia; Windelband, Lars

    2008-01-01

    Against the background of changing consumer behaviour and environmental policies, a growing second-hand sector is expected. In order to ensure quality and professionalism within companies operating in this sector, it is necessary to develop a unified Europewide and sector-specific qualification which is geared to real working processes and requirements. This good practice report describes the training and qualification structures in the European second-hand sector. In addition, occupational a...

  2. IEEE recommended practices for seismic qualification of Class 1E equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    The IEEE has developed this document to provide direction for developing programs to seismically qualify Class 1E equipment for nuclear power generating stations. It supplements IEEE Std 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for equipment qualification. The Class 1E equipment to be qualified by produres or standards established by this document are of many forms, characteristics, and materials; therefore, the document presents many acceptable methods with the intent of permitting the user to make a judicious selection from among the various options. In making such a selection, the user should choose those that best meet a particular equipment's requirements. Further, in using this document as a specification for the purchase of equipment, the many options should also be recognized and the document invoked accordingly. It is recommended that the need for specific standards for the seismic qualifiction of particular kinds of equipment be evaluated by those responsible for such documents and that consideration be given to the application of particular methods from these documents which are most suitable

  3. Nuclear power plant personnel entry level qualifications and training

    International Nuclear Information System (INIS)

    Jorgensen, C.C.; Haas, P.M.; Selby, D.L.; Lowry, J.C.

    1983-01-01

    This paper summarizes the early results and current status of a research program at ORNL which is intended to provide the methods and technical basis for NRC to initiate the use of the Systems Approach to Training (SAT) in the evaluation of training programs and entry level qualifications for NPP control room personnel. The program is an outgrowth of previous studies of simulator hardware and simulator training requirements under the Safety Related Operator Actions Program which recommended adaptation of a systems methodology to development and evaluation of NPP training programs

  4. Design Modification of Kori Unit 1 for the Equipment Qualification

    International Nuclear Information System (INIS)

    Park, J. W.; Kim, M. Y.; Han, K. T.; Park, J. D.

    2007-01-01

    There has not been a strict regulatory requirements for the Equipment Qualification(EQ) in 1970's when Kori Unit 1 had begun the construction and the commercial operation. The Korean regulatory body requested the EQ on the various safety-related components, as a result of Periodic Safety Review. However, the EQ itself is impossible in some areas, due to the high pressure/temperature and flooding environment conditions from the pipe breaks. Design modification is being considered in the Auxiliary Building, the Intermediate Building, the Component Cooling Water Heat Exchanger Building and the Turbine Building, in order to mitigate the environmental conditions for the EQ

  5. EFFECTIVENESS OF SELECTION OF WHEAT TO MODERN REQUIREMENTS FOR SUSTAINABLE DEVELOPMENT OF AGRICULTURE III. ENERGY PRODUCTIVITY OF CROPS

    Directory of Open Access Journals (Sweden)

    Elisaveta Vasileva

    2014-03-01

    Full Text Available Aim of the study was to conclude on adaptation of modern varieties to the requirements of sustainable agriculture and hence the effectiveness of their methods of selection with respect to these requirements. The comparison between genotypes in two directions - by the selection methods by which they were established and according to the time of their creation. Energy assessment shows that the gross energy yield of grain is higher ( in average 5% over standard for varieties produced by the methods of the Intervarietal hybridization and during the period 1995 to 1999. While absolute maximum values of the energy productivity of grain (at N18 and maximum average total gross energy productivity of crops (4% above standard were detected in genotypes generated by the methods of mutagenesis by irradiation with gamma rays. Absolute maximum value of the energy productivity of crops were reported in cultivar Zdravko (at N18, which was established by the method of plant biotechnology by combining and somaclonal variation.

  6. Mechanical design and qualification of IR filter mounts and filter wheel of INSAT-3D sounder for low temperature

    Science.gov (United States)

    Vora, A. P.; Rami, J. B.; Hait, A. K.; Dewan, C. P.; Subrahmanyam, D.; Kirankumar, A. S.

    2017-11-01

    Next generation Indian Meteorological Satellite will carry Sounder instrument having subsystem of filter wheel measuring Ø260mm and carrying 18 filters arranged in three concentric rings. These filters made from Germanium, are used to separate spectral channels in IR band. Filter wheel is required to be cooled to 214K and rotated at 600 rpm. This Paper discusses the challenges faced in mechanical design of the filter wheel, mainly filter mount design to protect brittle germanium filters from failure under stresses due to very low temperature, compactness of the wheel and casings for improved thermal efficiency, survival under vibration loads and material selection to keep it lighter in weight. Properties of Titanium, Kovar, Invar and Aluminium materials are considered for design. The mount has been designed to accommodate both thermal and dynamic loadings without introducing significant aberrations into the optics or incurring permanent alignment shifts. Detailed finite element analysis of mounts was carried out for stress verification. Results of the qualification tests are discussed for given temperature range of 100K and vibration loads of 12g in Sine and 11.8grms in Random at mount level. Results of the filter wheel qualification as mounted in Electro Optics Module (EOM) are also presented.

  7. TEACHERS’ EDUCATIONAL QUALIFICATION, RANK LEVEL, WORKING DURATION, AGE, WORK MOTIVATION AND WORK EFFECTIVENESS

    Directory of Open Access Journals (Sweden)

    Bambang Budi Wiyono

    2016-02-01

    Full Text Available Teachers’ Educational Qualification, Rank Level, Working Duration, Age, Working Mo­tivation, and Working Effectiveness The study investigated the effects of educational qualification, rank level, working duration and age on the elementary school teachers’ working motivation and working ef­fectiveness. The sample of the study consisted of 438 elementary school teachers in Malang which were selected through cluster sampling technique. The study was conducted using explanatory design in the form of causal model. The data were collected using questionnaire and documentation, and were analyzed descrip­tively employing structural equation technique. The study revealed that that the effect of the educational qualification, rank level, working duration and age on teachers’ working motivation and working effec­tiveness, both directly and indirectly, was not significant.

  8. [Regarding Authorized Qualifications in Sonography].

    Science.gov (United States)

    Kaneko, Kazuhiko

    2015-04-01

    Today, I will talk about the profession "Ultrasound Technologist." The written examination to gain this license includes clinical questions (35 questions including those using photographs; 70 minutes to answer) and basic questions related to ultrasound for medical use (35 questions including those requiring calculation; 70 minutes to answer). The answer to each question is selected from 5 alternatives. The questions used in the examination are not officially disclosed. The minimum score needed to pass the examination is 60 points for both the test with clinical questions and that with basic questions. My practice to prepare for the basic questions related to ultrasound for medical use involved attempting to answer a collection of questions while understanding physical phenomena by watching animations on the related Internet homepage. I wrote down how to approach the questions (including those requiring calculation), together with comments and answers to each of them. Basic questions about ultrasound for medical use differ little from year to year because there are few questions reflecting highlights or specific topics prevailing in a given year. So, to prepare for basic questions, I think it is important to become familiar with the trends of questions and how to answer them through repeating mock tests many times. Preparing for clinical questions is very difficult. Although many collections of clinical questions are available at bookstores, I have the impression that most of the questions in these collections have already been used in past examinations, and there is now a tendency for more precise clinical questions targeting specific areas to be adopted for the examination. The questions adopted in the past are becoming outdated, while the techniques of ultrasonography are continuing to advance. So, clinical questions are being increasingly adopted that cover recent topics in this field. In any event, knowledge covering extensive areas is needed to prepare for the

  9. Seismic qualification of piping systems based on strain criteria

    International Nuclear Information System (INIS)

    Peters, K.; Rangette, A.

    1988-01-01

    Typical LMFBR piping is characterized by elevated temperature and low pressure levels. Taking into account operational conditions only these characteristics demand for and allow flexible piping design. The overestimation of the damage potential of seismic loading by e.g. improper failure criteria usually contradicts operational needs producing the known result of excessive ''snubberism'' and reduction of operational margins. As a matter of fact, due to its transiency seismic loading is essentially secondary provoking the natural design requirement ductility instead of stiffness and rigidity - i.e. exclusion of failure by strain control instead of stress control - and thus avoiding the LMFBR typical competition between operational needs and seismic qualification. The design requirement ductility needs judgement mechanisms, i.e. suitable load descriptions, allowed strain levels and strain evaluation tools. A simplified method for strain range estimation and the underlying basic ideas are roughly outlined. The status of verification and experience gained so far is described. The results achieved suggest that the qualification of piping based on ductility requirement controlled by strain criteria is not out of reach. (author)

  10. Mechanical properties used for the qualification of transport casks

    International Nuclear Information System (INIS)

    Salzbrenner, R.; Crenshaw, T.B.; Sorenson, K.B.

    1993-01-01

    The qualification process that should be sufficient for qualification of a specific cask (material/geometry combination) has been examined. The prototype cask should be tested to determine its overall variation in microstructure, chemistry, and mechanical properties. This prototype may also be subjected to 'proof testing' to demonstrate the validity of the design analysis (including the mechanical properties used in the analysis). The complete mechanical property mapping does not necessarily have to precede the proof testing (i.e., portions of the cask which experience only low (elastic) loads during the drop test are suitable for mechanical test specimens). The behavior of the prototype cask and the production casks are linked by assuring that each cask possesses at least the minimum level of one or more critical mechanical properties. This may be done by measuring the properties of interest directly, or by relying on a secondary measurement (such as subsize mechanical test results or microstructure/compositional measurements) which has been statistically correlated to the critical properties. The database required to show the correlation between the secondary measurement and the valid design property may be established by tests on the material from the prototype cask. The production controls must be demonstrated as being adequate to assure that a uniform product is produced. The testing of coring (or test block or prolongation) samples can only be viewed as providing a valid link to the benchmark results provided by the prototype cask if the process used to create follow-on casks remains essentially similar. The MOSAIK Test Program has demonstrated the qualification method through the benchmarking stage. The program did not establish for qualifying serial production casks through, for example, a correlation between small specimen parameters and valid design fracture toughness properties. Such a correlation would require additional experimental work. (J.P.N.)

  11. SRS H1616 Hydride Transport Vessel Qualification Report

    International Nuclear Information System (INIS)

    Smith, A.C.

    1999-01-01

    This report serves as the design qualification basis for both transport and facility use. Headings identify report sections as containing qualification information for transport use, facility use, or both transport and facility use

  12. SRS H1616 Hydride Transport Vessel Qualification Report

    International Nuclear Information System (INIS)

    Van Alstine, M.N.

    1998-01-01

    This report serves as the design qualification basis for both transport and facility use. Headings identify report sections as containing qualification information for transport use, facility use, or both transport and facility use

  13. Global Trend In The Qualifications Of Medical Educators | Issa ...

    African Journals Online (AJOL)

    NPMCN) or its equivalents is the highest educational and professional qualification of clinical Medical Educators in Nigeria while PhD is the acceptable highest qualification for their basic medical sciences counterparts. This had been the status ...

  14. LTP fibre injector qualification and status

    International Nuclear Information System (INIS)

    Bogenstahl, J; Cunningham, L; Fitzsimons, E D; Hough, J; Killow, C J; Perreur-Lloyd, M; Robertson, D; Rowan, S; Ward, H

    2009-01-01

    This paper presents the current state of the LISA Technology Package (LTP) fibre injector qualification project in terms of vibration and shock tests. The fibre injector is a custom built part and therefore must undergo a full space qualification process. The mounting structure and method for sinusoidal vibration and random vibration tests as well as shock tests will be presented. Furthermore a proposal will be presented to use the fibre injector pair qualification model to build an optical prototype bench. The optical prototype bench is a full-scale model of the flight model. It will be used for development and rehearsal of all the assembly stages of the flight model and will provide an on-ground simulator for investigation as an updated engineering model.

  15. Non-destructive qualification tests for ITER cryogenic axial insulating breaks

    International Nuclear Information System (INIS)

    Kosek, Jacek; Lopez, Roberto; Tommasini, Davide; Rodriguez-Mateos, Felix

    2014-01-01

    In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes

  16. Training and qualification program for nuclear criticality safety technical staff. Revision 1

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1997-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

  17. Qualification of a production and packaging hot cell for sodium pertechnetate Tc 99m

    International Nuclear Information System (INIS)

    Cavero, Luis; Robles, Anita; Miranda, Jesus; Martinez, Ramos; Paragulla, Wilson; Moore, Mariel; Herrera, Jorge; Ocana, Elias; Portilla, Arturo; Otero, Manuel; Novoa, Carlos; Koga, Roberto

    2014-01-01

    It was designed and implemented a protocol for a hot cell of production and packaging of sodium pertechnetate Tc 99m, in a two-step process: installation qualification (IQ) and operation qualification (OQ). In the IQ design specifications and user requirements and associated equipment and materials by traceable documentation was verified. In the OQ scheduled for operation and control sequences it was verified plus operational tests recommended by the World Health Organization (WHO) and ISO 14644-1 and 3 were performed to clean areas. The results showed that the hot cell complies with the classification for Grades C and A for the preparation and packaging of Tc 99m. (authors).

  18. Staff report on the environmental qualification of safety-related electrical equipment

    International Nuclear Information System (INIS)

    1977-12-01

    The current NRC safety review process for nuclear power plants includes criteria related to the qualification of certain electrical equipment. These criteria require that electrical equipment important to safety must be qualified to function in the environment that might result from various accident conditions. Although such criteria have been applied since the early days of commercial nuclear power, the details of these criteria have been changed over the years. The evolution of environmental qualification of safety-related electrical equipment is described in Appendix A

  19. Importance of the European qualification frame (EQF) and its tools for radiation protection

    International Nuclear Information System (INIS)

    Schmitt-Hannig, Annemarie

    2013-01-01

    The harmonization of different radiation protection education and training systems in Europe and the mutual approval of the qualifications acquired abroad are discussed since years. Due to large national differences the mutual approval is usually based on case approaches instead of a standardized procedure. With the European qualification frame for life learning and EVCET (European credit system for vocational education and training) there are tools that could also be used in the sector of radiation protection education and training. The draft of the EURATOM basic safety standards (BSS) guideline includes the requirement of an approval of radiation protection officer certifications.

  20. Development, structure and qualification of a new digital instrumentation and control system

    International Nuclear Information System (INIS)

    Hofmann, H.; Sauer, H.J.

    1991-01-01

    Introduction of digital instrumentation and control in nuclear power plants is characterized by the need to meet numerous requirements concerning reliability, ergonomic design of the main control room and comprehensive qualification. The system described here is distinguished by a hierarchical and modular structure, being redundant throughout. Ergonomic considerations dominate the layout of the screen-based main control room. Powerful computer-aided engineering tools are employed for planning of the entire system and for generation of the user software. Qualification is performed in step with the development of the system, based on the applicable national and international rules and regulations and in close cooperation with an independent expert. (orig.) [de

  1. Non-destructive qualification tests for ITER cryogenic axial insulating breaks

    Energy Technology Data Exchange (ETDEWEB)

    Kosek, Jacek [Wroclaw University of Technology, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw, Poland and CERN, Geneva 23,CH-1211 (Switzerland); Lopez, Roberto; Tommasini, Davide [CERN, Geneva 23,CH-1211 (Switzerland); Rodriguez-Mateos, Felix [CERN, Geneva 23,CH-1211, Switzerland and ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France)

    2014-01-29

    In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes.

  2. Equipment qualification testing methodology research at Sandia Laboratories

    International Nuclear Information System (INIS)

    Jeppesen, D.

    1983-01-01

    The Equipment Qualification Research Testing (EQRT) program is an evolutionary outgrowth of the Qualification Testing Evaluation (QTE) program at Sandia. The primary emphasis of the program has been qualification methodology research. The EQRT program offers to the industry a research-oriented perspective on qualification-related component performance, as well as refinements to component testing standards which are based upon actual component testing research

  3. CLASSIFICATION OF SPECIALTIES AND QUALIFICATIONS IN REPUBLIC OF BELARUS: TENDENCIES AND PROSPECTS

    Directory of Open Access Journals (Sweden)

    O. A. Oleks

    2016-01-01

    Full Text Available In the present publication short data on the system of specialties and qualifications functioning in Republic of Belarus, her features, scope of application are given. The purpose and problems of the revision of the National classifier of the Republic of Belarus «Specialties and qualifications», its orientation to reduce the gap between the content of education and content of activity of graduates of establishments of education are described. The main tendencies of change of the operating classification – on the basis of types of economic activity and international standard classification of education taking into account requirements of employers, minimization of economic expenses for education, including due to minimization of classification units, rapprochement of positions with educational systems of other states are revealed. Prospects of development of national system of specialties and qualifications are disclosed. Tendencies and prospects of the expected changes are shown on the examples of the certain specialties offered by BNTU (Belarusian National Technical University.

  4. Qualification by analogy of the functional valving of French pressurized water nuclear power stations

    International Nuclear Information System (INIS)

    Grenet, M.

    1991-01-01

    In certain postulated accidental conditions (loss of coolant accident or secondary pipe rupture, earthquake, high energy pipe rupture) plant valving is called on the important functions to bring the reactor to and maintain it at a safe shutdown condition. ELWCTRICITE DE FRANCE has completed qualification tests of about forty valves to assure their operability. However, taking into account the costs and time required to obtain this qualification and the number of valves to be qualified, this method alone is not sufficient. For this reason, Electricite de France has developed the alternative qualification methodology by analogy for each postulated accidental situation. Feedback experience of these methods today is such that it can be they have achieved their objective; namely, to improve the safety of French pressurized water nuclear power stations, while at the same time avoiding the two dangers represented by excessive complexity resulting in unsatisfactory operation, and insufficient thoroughness not providing any real increase in safety. (author)

  5. Accounting Professor Qualification in Digital Age: A Perception Study on Brazilian Professors

    Science.gov (United States)

    Vendruscolo, Maria Ivanice; Behar, Patrícia Alejandra

    2015-01-01

    This papers aims at analyzing the perception of Accounting professors about the necessary qualifications in Accounting undergraduate courses. The contribution of this study is to theoretically discuss the education of Accounting professors, with empirical data, because Accounting teaching requires specific competencies in the digital area. The…

  6. 26 CFR 1.6036-1 - Notice of qualification as executor or receiver.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 13 2010-04-01 2010-04-01 false Notice of qualification as executor or receiver. 1.6036-1 Section 1.6036-1 Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE TREASURY... executor or receiver. For provisions relating to the notice required of fiduciaries, see the regulations...

  7. The Returns to Completion or Partial Completion of a Qualification in the Trades. Research Report

    Science.gov (United States)

    Lu, Tham

    2015-01-01

    Many students do not complete full qualifications in the vocational education and training (VET) system because their intention is to obtain only the particular skills they require. This can be achieved through the acquisition of skill sets; these enable flexibility in training to quickly respond to changes in the labour market. Skill sets may…

  8. 76 FR 20351 - Federal Acquisition Regulation; Information Collection; Architect-Engineer Qualifications (SF 330)

    Science.gov (United States)

    2011-04-12

    ...; Information Collection; Architect-Engineer Qualifications (SF 330) AGENCIES: Department of Defense (DOD... approve an extension of a currently approved information collection requirement for the Architect-Engineer... Standard Form 330, Part I is used by all Executive agencies to obtain information from architect-engineer...

  9. 76 FR 55389 - Federal Acquisition Regulation; Submission for OMB Review; Architect-Engineer Qualifications (SF...

    Science.gov (United States)

    2011-09-07

    ...; Submission for OMB Review; Architect-Engineer Qualifications (SF 330) AGENCIES: Department of Defense (DOD... extension of a previously approved information collection requirement for the Architect-Engineer... 330, Part I is used by all Executive agencies to obtain information from architect-engineer firms...

  10. 24 CFR 92.252 - Qualification as affordable housing: Rental housing.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Qualification as affordable housing: Rental housing. 92.252 Section 92.252 Housing and Urban Development Office of the Secretary, Department of Housing and Urban Development HOME INVESTMENT PARTNERSHIPS PROGRAM Project Requirements § 92.252...

  11. Minimum qualifications for nuclear criticality safety professionals

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1990-01-01

    A Nuclear Criticality Technology and Safety Training Committee has been established within the U.S. Department of Energy (DOE) Nuclear Criticality Safety and Technology Project to review and, if necessary, develop standards for the training of personnel involved in nuclear criticality safety (NCS). The committee is exploring the need for developing a standard or other mechanism for establishing minimum qualifications for NCS professionals. The development of standards and regulatory guides for nuclear power plant personnel may serve as a guide in developing the minimum qualifications for NCS professionals

  12. 5 CFR 317.502 - Qualifications Review Board certification.

    Science.gov (United States)

    2010-01-01

    ... REGULATIONS EMPLOYMENT IN THE SENIOR EXECUTIVE SERVICE Career Appointments § 317.502 Qualifications Review Board certification. (a) A Qualification Review Board (QRB) convened by OPM must certify the executive... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Qualifications Review Board certification...

  13. 49 CFR 214.351 - Training and qualification of flagmen.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification of flagmen. 214.351... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.351 Training and qualification of flagmen. (a) The training and qualification for roadway workers assigned the...

  14. Return of IEEE Std 627 and its Value to Equipment Qualification Programs

    International Nuclear Information System (INIS)

    Horvath, D.A.

    2012-01-01

    IEEE Std 627 ''Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations'' was issued to more generically establish qualification requirements in the form of a high level umbrella document. Efforts on this standard began in late 1975 at the request of the IEEE Nuclear Standards Management Board. In 1977 a joint ASME/IEEE agreement established responsibility for qualification and quality assurance standards preparation. ASME accepted responsibility for Quality Assurance and IEEE for qualification. In accordance with that agreement, IEEE completed the generic qualification standard in 1980. This document provided high level approaches, criteria, guidance, and principles for qualification of both electrical and mechanical equipment that at that time appeared in no other industry standard. IEEE Std 627-1980 was later reaffirmed in 1996. In 1986, ASME's Board on Nuclear Codes and Standards directed its Committee on Qualification of Mechanical Equipment (QME) to develop a standard for qualifying mechanical equipment. This task was completed in several parts during the time frame from 1992 to 1994. Partly in response to this activity, IEEE Std 627 was withdrawn in 2002. Later although withdrawn, it was found that IEEE Std 627 was continuing to be used and referenced by many entities both in the US and other countries including in ASME's QME-1-2002 ''Qualification of Active Mechanical Equipment Used in Nuclear Power Plants'', US NRC's NUREG-0800 Standard Review Plan Section 3.11, at least one reactor vendor's Design Certification Document (DCD), several international licensing documents, and elsewhere. As a result, in 2007, the IEEE Standards Board authorized Working Group 2.10 of Subcommittee 2 (Qualification) of the Power and Energy Society's Nuclear Power Engineering Committee to resurrect and update IEEE Std 627-1980 (Reaff 1996). The result was the culmination IEEE Std 627 in 2010. This paper will report on the eight improvements made

  15. Seismic qualification of equipment in operating nuclear power plants: Unresolved Safety Issue A-46

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46. In addition, the collection and review of seismic experience data and existing seismic test data are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experienced data base. The principal technical finding of USI A-46 is that seismic experience data, supplemented by existing seismic test data, applied in accordance with the guidelines developed, can be used to verify the seismic adequacy of mechanical and electrical equipment in operating nuclear plants. Explicit seismic qualification should be required only if seismic experience data or existing test data on similar components cannot be shown to apply

  16. Space qualification of high capacity grooved heat pipes

    Energy Technology Data Exchange (ETDEWEB)

    Dubois, M; Mullender, B; Druart, J [SABCA, Societe Anomyme Belgel de Construction Aeronautique (Belgium); Supper, W; Beddows, A [ESTEC-The (Netherlands)

    1997-12-31

    Based on the thermal requirements of the future telecommunication satellites, the development of a High Capacity Grooved Heat Pipe (HPG), was contracted by ESA to SABCA leading to an aluminium extruded heat pipe (outer diameter of 25 mm) based on a multi re-entrant grooves design. After an intensive acceptance test campaign whose results showed a good confidence in the design and the fulfillment of the required specifications of heat transport and on tilt capability (experimental maximum heat transport capability of 1500 Watt metres for a vapour temperature of 20 deg C), similar heat pipes have been developed with various outer diameters (11 mm, 15 mm and 20 mm) and with various shapes (circular outer shapes, integrated saddles). Several of these heat pipes were tested during two parabolic flight campaigns, by varying the heat loads during the micro-gravity periods. This HGP heat pipe family is now being submitted to a space qualification program according to ESA standards (ESA PSS-49), both in straight and bent configuration. Within this qualification, the heat pipes are submitted to an extended test campaign including environmental (random/sinus vibration, constant acceleration) and thermal tests (thermal performance, thermal cycle, thermal soak, ageing). (authors) 9 refs.

  17. Space qualification of high capacity grooved heat pipes

    Energy Technology Data Exchange (ETDEWEB)

    Dubois, M.; Mullender, B.; Druart, J. [SABCA, Societe Anomyme Belgel de Construction Aeronautique (Belgium); Supper, W.; Beddows, A. [ESTEC-The (Netherlands)

    1996-12-31

    Based on the thermal requirements of the future telecommunication satellites, the development of a High Capacity Grooved Heat Pipe (HPG), was contracted by ESA to SABCA leading to an aluminium extruded heat pipe (outer diameter of 25 mm) based on a multi re-entrant grooves design. After an intensive acceptance test campaign whose results showed a good confidence in the design and the fulfillment of the required specifications of heat transport and on tilt capability (experimental maximum heat transport capability of 1500 Watt metres for a vapour temperature of 20 deg C), similar heat pipes have been developed with various outer diameters (11 mm, 15 mm and 20 mm) and with various shapes (circular outer shapes, integrated saddles). Several of these heat pipes were tested during two parabolic flight campaigns, by varying the heat loads during the micro-gravity periods. This HGP heat pipe family is now being submitted to a space qualification program according to ESA standards (ESA PSS-49), both in straight and bent configuration. Within this qualification, the heat pipes are submitted to an extended test campaign including environmental (random/sinus vibration, constant acceleration) and thermal tests (thermal performance, thermal cycle, thermal soak, ageing). (authors) 9 refs.

  18. Techniques and tools for software qualification in KNICS

    International Nuclear Information System (INIS)

    Cha, Kyung H.; Lee, Yeong J.; Cheon, Se W.; Kim, Jang Y.; Lee, Jang S.; Kwon, Kee C.

    2004-01-01

    This paper describes techniques and tools for qualifying safety software in Korea Nuclear Instrumentation and Control System (KNICS). Safety software are developed and applied for a Reactor Protection System (RPS), an Engineered Safety Features and Component Control System (ESF-CCS), and a safety Programmable Logic Controller (PLC) in the KNICS. Requirements and design specifications of safety software are written by both natural language and formal specification languages. Statechart is used for formal specification of software of the ESF-CCS and the safety PLC while NuSCR is used for formal specification of them of the RPS. pSET (POSCON Software Engineering Tool) as a software development tool has been developed and utilized for the IEC61131-3 based PLC programming. The qualification of the safety software consists of software verification and validation (V and V) through software life cycle, software safety analysis, and software configuration management, software quality assurance, and COTS (Commercial-Off-The-Shelf) dedication. The criteria and requirements for qualifying the safety software have been established with them in Software Review Plan (SRP)/Branch Technical Positions (BTP)-14, IEEE Std. 7-4.3.2-1998, NUREG/CR-6463, IEEE Std. 1012-1998, and so on. Figure 1 summarizes qualification techniques and tools for the safety software

  19. Qualification, certification and training of quality assurance personnel

    International Nuclear Information System (INIS)

    Ribeiro da Costa, J.

    1982-01-01

    The qualification and certification of technical personnel for activities related to nuclear quality is one of the most critical problems in developing countries which use nuclear power for peaceful purposes. A careful analysis of industrial quality levels is required in order to determine existing weaknesses, to correct deviations and to regulate quality-related activities so that nuclear power programmes can be implemented with no difficulties other than those inherent in the very complexity of nuclear technology. In this connection, indoctrination, training and qualification of technical personnel, in line with the requirements to quality assurance (QA), are tasks which must be undertaken right at the outset, taking into account the country's stage of technological development, its objectives and the necessity to increase its direct participation in QA activities in the shortest possible time. The paper shows how the problem was approached in Brazil, beginning with an analysis of the situation of industry in this field, the evolution of QA training programmes through several stages, leading to systematic training in the field of nuclear quality and, finally, the introduction of training in the more specific and sophisticated field of nuclear reliability. (author)

  20. Empirical Selection of Informative Microsatellite Markers within Co-ancestry Pig Populations Is Required for Improving the Individual Assignment Efficiency

    Directory of Open Access Journals (Sweden)

    Y. H. Li

    2014-05-01

    Full Text Available The Lanyu is a miniature pig breed indigenous to Lanyu Island, Taiwan. It is distantly related to Asian and European pig breeds. It has been inbred to generate two breeds and crossed with Landrace and Duroc to produce two hybrids for laboratory use. Selecting sets of informative genetic markers to track the genetic qualities of laboratory animals and stud stock is an important function of genetic databases. For more than two decades, Lanyu derived breeds of common ancestry and crossbreeds have been used to examine the effectiveness of genetic marker selection and optimal approaches for individual assignment. In this paper, these pigs and the following breeds: Berkshire, Duroc, Landrace and Yorkshire, Meishan and Taoyuan, TLRI Black Pig No. 1, and Kaohsiung Animal Propagation Station Black pig are studied to build a genetic reference database. Nineteen microsatellite markers (loci provide information on genetic variation and differentiation among studied breeds. High differentiation index (FST and Cavalli-Sforza chord distances give genetic differentiation among breeds, including Lanyu’s inbred populations. Inbreeding values (FIS show that Lanyu and its derived inbred breeds have significant loss of heterozygosity. Individual assignment testing of 352 animals was done with different numbers of microsatellite markers in this study. The testing assigned 99% of the animals successfully into their correct reference populations based on 9 to 14 markers ranking D-scores, allelic number, expected heterozygosity (HE or FST, respectively. All miss-assigned individuals came from close lineage Lanyu breeds. To improve individual assignment among close lineage breeds, microsatellite markers selected from Lanyu populations with high polymorphic, heterozygosity, FST and D-scores were used. Only 6 to 8 markers ranking HE, FST or allelic number were required to obtain 99% assignment accuracy. This result suggests empirical examination of assignment-error rates

  1. Towards a systematic format for (seismic) equipment qualification standards

    International Nuclear Information System (INIS)

    Smith, P.D.

    1982-01-01

    As part of technical assistance to the US Nuclear Regulatory Commission (NRC, 1), a systematic format for seismic equipment qualification (EQ) was initiated. This format consists of thirty issues associated with seismic EQ. Each issue was considered as a Category of Possible Seismic EQ Requirements and Criteria. That is, seismic EQ standards might be (but presently are not formulated in terms of requirements and criteria that address each of the thirty issues. Each of the thirty issues was ranked and a minimum set identified. The current requirements in existing NRC and national standards were also evaluated against this common set of issues, and they were estimated to score 60 out of 100 overall. It is believed that the systematic format exhibited in this paper can be of assistance in obtaining a broader and more complete perspective on seismic EQ issues. This format (but especially the technique) may also be of interest in non-seismic EQ since many of the issues are common

  2. AGC-2 Irradiation Data Qualification Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Laurence C. Hull

    2012-07-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The second Advanced Graphite Creep (AGC) experiment (AGC-2) began with Advanced Test Reactor (ATR) Cycle 149A on April 12, 2011, and ended with ATR Cycle 151B on May 5, 2012. The purpose of this report is to qualify AGC-2 irradiation monitoring data following INL Management and Control Procedure 2691, Data Qualification. Data that are Qualified meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Data that do not meet the requirements are Failed. Some data may not quite meet the requirements, but may still provide some useable information. These data are labeled as Trend. No Trend data were identified for the AGC-2 experiment. All thermocouples functioned throughout the AGC-2 experiment. There was one instance where spurious signals or instrument power interruption resulted in a recorded temperature value being well outside physical reality. This value was identified and labeled as Failed data. All other temperature data are Qualified. All helium and argon gas flow data are within expected ranges. Total gas flow was approximately 50 sccm through the capsule. Helium gas flow was briefly increased to 100 sccm during reactor shutdown. All gas flow data are Qualified. At the start of the experiment, moisture in the outflow gas line increased to 200 ppmv then declined to less than 10 ppmv over a period of 5 days. This increase in moisture coincides with the initial heating of the experiment and drying of the system. Moisture slightly exceeded 10 ppmv three other times during the experiment. While these moisture values exceed the 10 ppmv threshold value, the reported measurements are considered accurate and to reflect moisture conditions in the capsule. All moisture data are Qualified. Graphite creep specimens are subjected to one of three loads, 393 lbf

  3. PROBLEMS OF COMPETENCY-BASED ASSESSMENT OF APPLIED QUALIFICATIONS

    Directory of Open Access Journals (Sweden)

    S. A. Efimova

    2017-01-01

    Full Text Available Introduction. The search of the unified tools of competences measurement of vocational training institutions graduates and identification of mechanisms of interrelation of these competences with requirements of professional standards imposed to workers of various levels are brought into focus in the context of formation of National system of qualifications of the Russian Federation, introduction of the Third-generation Federal State Educational Standards and transition of professional education to the modular, and competence-based model of the organization of training. The aim of the article is to justify the content, structure and technology of competency-based assessment, as a set of interrelated activities and regulated procedures performed on the basis of the standardized interdisciplinary evaluation materials. Methodology and research methods. The present investigation is based on systematic-activity and competency-based approaches, analysis, systematization, and generalization. Results. The place of competencies, as a part of educational outcomes of vocational education programs, is justified. Critical analysis of typical methodological solutions that are typical for the modern pedagogical practices of the competency-based assessment is performed. The content and organizational design of the process of competency-based assessment is described. Scientific novelty. The conceptual apparatus of competency-based assessment is supplemented with the «sub-competence» category - component of competence, which retains all of its properties due to human activities. Factors of objects choice and methods of assessment in identifying the professional competences are proved. Practical significance. Results of the study can be used by researchers involved with assessment procedures; methodologists and teachers of professional educational organizations, training institutes, independent centers of the qualifications evaluation for the organization of

  4. β-catenin is selectively required for the expansion and regeneration of mature pancreatic acinar cells in mice

    Directory of Open Access Journals (Sweden)

    Matthew D. Keefe

    2012-07-01

    The size of the pancreas is determined by intrinsic factors, such as the number of progenitor cells, and by extrinsic signals that control the fate and proliferation of those progenitors. Both the exocrine and endocrine compartments of the pancreas undergo dramatic expansion after birth and are capable of at least partial regeneration following injury. Whether the expansion of these lineages relies on similar mechanisms is unknown. Although we have shown that the Wnt signaling component β-catenin is selectively required in mouse embryos for the generation of exocrine acinar cells, this protein has been ascribed various functions in the postnatal pancreas, including proliferation and regeneration of islet as well as acinar cells. To address whether β-catenin remains important for the maintenance and expansion of mature acinar cells, we have established a system to follow the behavior and fate of β-catenin-deficient cells during postnatal growth and regeneration in mice. We find that β-catenin is continuously required for the establishment and maintenance of acinar cell mass, extending from embryonic specification through juvenile and adult self-renewal and regeneration. This requirement is not shared with islet cells, which proliferate and function normally in the absence of β-catenin. These results make distinct predictions for the relative role of Wnt–β-catenin signaling in the etiology of human endocrine and exocrine disease. We suggest that loss of Wnt–β-catenin activity is unlikely to drive islet dysfunction, as occurs in type 2 diabetes, but that β-catenin is likely to promote human acinar cell proliferation following injury, and might therefore contribute to the resolution of acute or chronic pancreatitis.

  5. Guidelines for training and qualification of radiological protection technicians

    International Nuclear Information System (INIS)

    1987-08-01

    These guidelines, used in combination with plant-specific job analysis, provide the framework for a training and qualification program for radiological protection technicians at nuclear power plants. Radiological protection technicians are defined as those individuals, both plant and contractor, who will be engaged in the evaluation of radiological conditions in the nuclear plant and the implementation of the necessary radiological safety measures as they apply to nuclear plant workers and members of the general public. An important aspect of this work is recognizing and handling unusual situations involving radioactivity, including incidents related to degraded core conditions. These guidelines incorporate the results of an industry-wide job analysis and task analysis (JTA) combined with industry operating experience review. However, the industry-wide analyses did not identify all important academic and fundamental knowledge and skills. Further in-depth analysis by subject matter experts produced additional knowledge and skills that were added to these guidelines. All utilities should use these guidelines in conjunction with plant-specific and industry-wide JTA results to develop or validate their radiological protection technician training program. Plant-specific information should be used to establish appropriate training program content. This plant-specific information should reflect unique job duties, equipment, operating experience, and trainee entry-level qualifications. Revisions to these guidelines should be reviewed for applicability and incorporated into the training program using each utility's training system development (TSD) procedures. Plant-specific job analysis and task analysis data is essential to the development of performance-based training programs. These analyses are particularly useful in selecting tasks for training and in developing on-the-job training (OJT), laboratory training, and mock-up training. Qualification programs based on these

  6. DATA QUALIFICATION REPORT: DATA QUALIFICATION REPORT FOR 1991 1:1200 TOPOGRAPHIC MAPS FOR USE ON THE YUCCA MOUNTAIN PROJECT

    International Nuclear Information System (INIS)

    Knop, M.F.; Grant, T.A.; Bonisolli, R.W.

    2005-01-01

    This Data Qualification Report (DQR) is prepared in accordance with the provisions of AP-SIII.2Q, Rev. 0, ICN 3, Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data and Data Qualification Plan for 1991 Topographic Maps 1:1200 Scale for use on the Yucca Mountain Project, DQP-WHS-CI-000001, Rev. 00 (BSC 2002a). This DQR presents an evaluation of a set of 90 topographic sheets at 1:1200 scale (and an associated electronic file) that covers an approximate 18 square mile area surrounding the proposed Yucca Mountain Project repository surface facilities location in Midway Valley, Nevada. These maps, that require qualification, are now being used to determine the physical characteristics of watershed sub-areas, interconnecting channels, and drainage channel cross-sections for hydrologic engineering studies of the north portal pad and vicinity. The result of this effort is to qualify one data tracking number (DTN) containing the electronic version of the mapping data. This DTN is: M09906COV98462.000. Coverage: TOP02FTS. The underlying quality assurance (QA) issue associated with these topographic maps is that the maps were originally designated as not for use in the design of items important to safety, waste isolation, and/or of programmatic importance. The maps were therefore generated outside the U.S. Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) QA program. Based on a comparison with corroborating information, this report concludes that the topographic maps are qualified. The comparison found that the mapping was reasonably accurate when compared with other mapping and survey data within the coverage area of the maps. Relative map accuracy was found to be very good and suitable for the hydrologic engineering studies being considered. Absolute accuracy is good but could not be demonstrated to comply with national map accuracy standards. Point locations that require high absolute accuracy should be

  7. Qualification of the AUTOBUS Mod. 2 Code

    International Nuclear Information System (INIS)

    Ciarniello, U.; Peroni, P.

    1988-01-01

    The paper presents the qualification of AUTOBUS MOD.2 code. After a brief description of the code itself, all the critical experiments simulated by the code are illustrated to prove the accuracy of criticality calculation and power distribution. An interpretation of the results and a conclusion close this presentation

  8. Qualifications and Skills: The Organisational Perspective

    Science.gov (United States)

    Dafou, Efthimia

    2009-01-01

    This paper portrays the inferences that employers in Greece draw from particular aspects of study programmes, as recorded on educational qualifications. Based on semi-structured interviews with human resource managers in 37 industrial and service organisations and general directors of careers offices in eight higher education institutions, and…

  9. The Diploma Disease. Education, Qualification and Development.

    Science.gov (United States)

    Dore, Ronald

    The aims and motives of schooling are changing, and it is becoming more and more a ritualized process of qualification-earning. The underlying causes of this change are traced through the education histories of Britain, Japan, Sri Lanka, and Kenya. It is illustrated that the competitve scramble for scarce modern jobs has created a "backwash…

  10. STEM Leadership Qualification: Tomorrow's Leaders Today

    Science.gov (United States)

    Williams, Chris

    2009-01-01

    This article features the Science, Technology, Engineering and Mathematics (STEM) Leadership Qualification programme, developed by the Centre for Science Education (CSE) at Sheffield Hallam University in collaboration with Edexcel, which sets out to develop leadership skills and capabilities through contexts in STEM. With six units to complete…

  11. PR Faculty: What Are Their Qualifications?

    Science.gov (United States)

    Johnson, Thomas B.; Rabin, Kenneth

    1977-01-01

    Discusses a study designed to determine existing trends in the backgrounds and qualifications of public relations instructors and how these might affect public relations education. Available from: Public Relations Review, Ray Hiebert, Dean, College of Journalism, University of Maryland, College Park, MD 20742. (MH)

  12. 15 CFR 40.2 - Qualifications.

    Science.gov (United States)

    2010-01-01

    ... Qualifications. (a) To be eligible for a training grant at the Bureau of the Census the applicant must be: (1) A... training programs. (2) Able to speak, read, write, and understand the English language. (3) Sponsored by his government either directly with the United States or through a public international agency. (4...

  13. PROBLEMS OF QUALIFICATION OF MEDIATHION IN BRIBERY

    Directory of Open Access Journals (Sweden)

    Alexander Uskin

    2015-12-01

    Full Text Available The article analysed the controversial issues of qualification of actions of the intermediary in bribery under article 291.1 of the Criminal code, are the kinds of mediation depending on the subject of bribes. On the basis of analysis of legislative construction is concluded decriminalize mediation in bribery if the bribe amount is less than 25 thousand rubles.

  14. 18 CFR 292.203 - General requirements for qualification.

    Science.gov (United States)

    2010-04-01

    ... certification, pursuant to § 292.207(b)(1), that has been granted. (c) Hydroelectric small power production facilities located at a new dam or diversion. (1) A hydroelectric small power production facility that..., pursuant to § 292.207(b)(1), that has been granted. (c) Hydroelectric small power production facilities...

  15. 29 CFR 549.1 - Essential requirements for qualifications.

    Science.gov (United States)

    2010-07-01

    ... constitutes a definite program or arrangement in writing, communicated or made available to the employees.... (e) The amounts paid to individual employees are determined in accordance with a definite formula or... the Office of Management and Budget under control number 1215-0119) [18 FR 3292, June 10, 1953, as...

  16. 46 CFR 402.210 - Requirements and qualifications for registration.

    Science.gov (United States)

    2010-10-01

    ... medical doctor and reported on the form furnished by the Director. The examination report shall describe..., neurosyphilis, hemiplegia, paralysis or missing arm, leg, or eye, muteness or pronounced speech impairment...

  17. Employers’ View on Problems Related to Workforce Skills and Qualification

    Directory of Open Access Journals (Sweden)

    Klimplová Lenka

    2012-12-01

    Full Text Available The aim of this exploratory study is to reveal employers’ views on problems related to workforce human capital (skills and qualification. Where do employers themselves view the core of difficulties with ensuring adequately skilled workforce? Do they assign them to technological and organizational changes (a functional concept of job-specific human capital obsolescence, or do they see these problems as a result of other circumstances, such as macro-structural conditions or institutional settings? To answer these questions selected employers in mechanical engineering and information technology sectors in the Czech Republic were interviewed. The results show that the employers see the problems: 1 on the side of workforce – insufficient abilities and skills, exaggerated demands and low motivation; 2 as inadequate capacities and capabilities of the organization itself; 3 at macro-level as institutional shortcomings in the initial educational system and social benefits system. The problems related to workforce skills and qualification cannot be, thus, interpreted only in the functionalist view as job-specific human capital obsolescence, but the formulation of the problems is significantly affected by the institutional framework.

  18. Data Qualification Report For DTN: MO0012RIB00065.002, Parameter Values For Transfer Coefficients

    International Nuclear Information System (INIS)

    C.H. Tung

    2001-01-01

    A data-qualification evaluation was conducted on Reference Information Base (RIB) data set MOO0 12RIB00065.002, ''Parameter Values for Transfer Coefficients''. The corroborating data method was used to evaluate the data. This method was selected because it closely matches the literature-review method followed to select parameter values. Five criteria were considered when the corroborating method was used: adequacy of the corroborative literature, sufficiency of value-selection criteria, implementation of the selection criteria, documentation of the process, and whether the analysis was conducted in accordance with applicable quality assurance (QA) procedures. Three criteria were used when a literature review was not conducted: appropriate logic used to select parameters, documentation of the process, and whether the analysis was conducted in accordance with applicable QA procedures. The RIB data item, the associated Analysis and Model Report (AMR), the corroborative literature, and the results of an audit revision O/ICN--0 of the AMR were examined. All calculations and the selection process for all values were repeated and confirmed. The qualification team concluded: (1) A sufficient quantity of corroborative literature was reviewed and no additional literature was identified that should have been considered. (2) The selection criteria were sufficient and resulted in valid parameter values. (3) The process was well defined, adequately documented in the AMR, and correctly followed. (4) The analysis was developed in accordance with applicable QA procedures. No negative findings were documented that resulted in questions about the quality of the data. The qualification team therefore recommends that the qualification status of RIB data set MO0012RIB00065.002 be changed to qualified

  19. Comparison of IEEE383-2003 and IEC60505-2004 standards for harmonization of environmental qualification procedure of electric cable

    International Nuclear Information System (INIS)

    Kim, Jong Seog; Jeong, Sun Chul; Park, Kyung Heum; Jang, Kyung Nam

    2010-01-01

    Needs for harmonization of international equipment qualification(EQ) standards have been raised several years due to purchasing problem of nuclear equipment supplied from abroad country. To meet the regulatory requirement of domestic nuclear power plant, manufacturers have to qualify their equipment in accordance with each standard such as IEEE, IEC and RCC-E. Double qualification increase the equipment cost, which result in high construction cost. Even the unification of each standard have been discussed several years, we have got the long way to go yet. Comparison and harmonization of each international standard will give help to purchase the equipment qualified by not endorsed standard. Environmental qualification, seismic qualification and EMI/EMC qualification are major targets for harmonization. Since concern about cable qualification of 60 years life has been raised recently, harmonization of cable qualification standard also needs to be discussed. KEPRI launched a project for harmonization of EQ relative standards such as IEEE, IEC and RCC-E. A study for harmonization of IEEE323 and IEC60780 is known in progress by IEEE committee. In this paper, harmonization of international standards for cable qualification will be discussed. IEEE383 standard is qualification standard for electric cable broadly used in Asian pacific area while IEC60505 is mostly used in European area. Since these two standards have different requirements for environmental qualification of cable, problem can be happened in the plant site when they purchase cable qualified by not endorsed standard. IEEE383-2003 and IEC60505-2004 is the latest version of each standard. Comparison results and recommendations for harmonization of these two standards are introduced herein

  20. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    International Nuclear Information System (INIS)

    Herman, Connie C.

    2013-01-01

    The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: Limitations of mixing/blending capability of the Hanford Tank Farm; The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the

  1. Qualification of GPHS-RTG for the Galileo and Ulysses missions

    International Nuclear Information System (INIS)

    Cockfield, R.D.

    1986-01-01

    The General Purpose Heat Source - Radioisotope Thermoelectric Generator (GPHS-RTG)- was designed and built by General Electric under the sponsorship of the Department of Energy, Office of Special Nuclear Projects, to power both the Galileo and Ulysses spacecraft. Separate STS launches of these two spacecraft were planned for May, l986, but have now been delayed. Galileo will carry two RTGs, providing over 5l0 watts of electrical power at the end of a 4.2 year mission, and Ulysses' single RTG will provide over 250 watts of electrical power at the end of a 4.7 year mission. These power levels and mission durations may differ for delayed launch schedules. To ensure that the GPHS-RTG is qualified for the Galileo and Ulysses missions, a formal program, consisting of extensive analyses, inspections, demonstrations, and tests, was conducted. Requirements for qualification included such categories as electrical performance, life characteristics, dynamic capability, thermal characteristics, active cooling system performance, magnetic properties, nuclear criticality, gas management provisions, electrostatic cleanliness, mass properties, neutron emission rate, and micrometeoroid survivability. This paper addresses selected topics from this list and presents data to show that anticipated performance will meet or exceed design requirements as specified for a May, l986 launch

  2. Equipment Qualification and Environment Establishment for COTS Dedication of Safety Grade PC

    International Nuclear Information System (INIS)

    Ahn, Kwang Chul; Bin, Chang Sun; Kwon, Yoon Kwang; Kang, Shin Woo; Koh, Sung Won; Shon, Eui Chan; Jang, Hyun Doo; Song, Il Sup; Lee, Hyun Noh

    2010-08-01

    Safety grade PCs are required for protection systems of SKN 3 and 4 nuclear power plant and subsequent plants. Commercial grade item (CGI) dedication should be carried out to utilize a commercial PC as a safety grade PC of nuclear power plants. This project is aimed to perform the equipment qualification of the commercial PC, and review and improve the quality system of the PC supplier. As a result of the EQ for the CGI dedication, selected military PCs have passed the environment test, the seismic test, and the EMI test required for the digital controllers of nuclear plants. In addition, a walk-through of the quality system of the PC supplier, ISO 9001, was carried out and the quality system was improved. History data for the PC was gathered. As the analysis of the history data showed that operating experience time of the PC is longer than the plant life time, the history data could be used as an evidence of acceptance. After dedicated according to the CGI dedication process, military rugged PCs could be used for safety grade PCs

  3. AGR-1 Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Abbott, Machael

    2009-01-01

    Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

  4. Sensitive and selective culture medium for detection of environmental Clostridium difficile isolates without requirement for anaerobic culture conditions.

    Science.gov (United States)

    Cadnum, Jennifer L; Hurless, Kelly N; Deshpande, Abhishek; Nerandzic, Michelle M; Kundrapu, Sirisha; Donskey, Curtis J

    2014-09-01

    Effective and easy-to-use methods for detecting Clostridium difficile spore contamination would be useful for identifying environmental reservoirs and monitoring the effectiveness of room disinfection. Culture-based detection methods are sensitive for detecting C. difficile, but their utility is limited due to the requirement of anaerobic culture conditions and microbiological expertise. We developed a low-cost selective broth medium containing thioglycolic acid and l-cystine, termed C. difficile brucella broth with thioglycolic acid and l-cystine (CDBB-TC), for the detection of C. difficile from environmental specimens under aerobic culture conditions. The sensitivity and specificity of CDBB-TC (under aerobic culture conditions) were compared to those of CDBB (under anaerobic culture conditions) for the recovery of C. difficile from swabs collected from hospital room surfaces. CDBB-TC was significantly more sensitive than CDBB for recovering environmental C. difficile (36/41 [88%] versus 21/41 [51%], respectively; P = 0.006). C. difficile latex agglutination, an enzyme immunoassay for toxins A and B or glutamate dehydrogenase, and a PCR for toxin B genes were all effective as confirmatory tests. For 477 total environmental cultures, the specificity of CDBB-TC versus that of CDBB based upon false-positive yellow-color development of the medium without recovery of C. difficile was 100% (0 false-positive results) versus 96% (18 false-positive results), respectively. False-positive cultures for CDBB were attributable to the growth of anaerobic non-C. difficile organisms that did not grow in CDBB-TC. Our results suggest that CDBB-TC provides a sensitive and selective medium for the recovery of C. difficile organisms from environmental samples, without the need for anaerobic culture conditions. Copyright © 2014, American Society for Microbiology. All Rights Reserved.

  5. Code qualification of structural materials for AFCI advanced recycling reactors.

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L. (Nuclear Engineering Division); (ORNL)

    2012-05-31

    This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Code Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP

  6. Selective orthosteric free fatty acid receptor 2 (FFA2) agonists: identification of the structural and chemical requirements for selective activation of FFA2 versus FFA3

    DEFF Research Database (Denmark)

    Schmidt, Johannes; Smith, Nicola J; Christiansen, Elisabeth

    2011-01-01

    given its size. Propionate, however, does not discriminate between FFA2 and the closely related receptor FFA3 (GPR41). To identify FFA2 selective ligands and understand the molecular basis for FFA2 selectivity, a targeted library of small carboxylic acids (SCAs) was examined using holistic, label...

  7. Round table discussion " Development of qualification framework in meteorology (TEMPUS QUALIMET)"

    Science.gov (United States)

    Bashmakova, I.; Belotserkovsky, A.; Karlin, L.; Petrosyan, A.; Serditova, N.; Zilitinkevich, S.

    2010-09-01

    The international consortium has started implementing a project aimed at the development of unified framework of qualifications in meteorology (QualiMet), setting a system of recognition and award of qualifications up to Doctoral level based on standards of knowledge, skill and competence acquired by learners is underway. The QualiMet has the following specific objectives: 1. To develop standards of knowledge, skills and competence for all qualifications up to Doctoral level needed in all possible occupations meteorology learner can undertake, by July 2011 2. To develop reciprocally recognized rubrics, criteria, methods and tools for assessing the compliance with the developed standards (quality assurance), by July 2012 3. To set the network of Centers of Excellence as the primary designer of sample education programs and learning experiences, both in brick-and-mortar and distant setting of delivery, leading to achievement of the developed standards, by December 2012 4. To set a system of mutual international recognition and award of qualifications in meteorology based on the developed procedures and establishment of self-regulatory public organization, by December 2012 The main beneficiaries of the project are: 1. Meteorology learners from the consortium countries. They will be able to make informed decisions about available qualification choices and progression options and provided an opportunity for students and graduates to participate in the system of international continuous education. 2. Meteorology employers from the consortium countries, They will be able to specify the level of knowledge, skill and competence required for occupational roles, evaluate qualifications presented, connect training and development with business needs. 3. Students and academic staff of all the consortium members, who will gain the increased mobility and exchange the fluxes of culturally and institutionally diversified lecturers and qualified specialists

  8. Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1985-08-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

  9. Seismic functional qualification of active mechanical and electrical components based on shaking table testing

    International Nuclear Information System (INIS)

    Jurukovski, D.

    1999-01-01

    The seismic testing for qualification of one sample of the NPP Kozloduy Control Panel type YKTC was carried out under Research Contract no: 8008/Rl, entitled: 'Seismic Functional Qualification of Active Mechanical and Electrical Components Based on Shaking Table Testing'. The tested specimen was selected by the Kozloduy NPP staff, Section 'TIA-2' (Technical Instrumentation and Automatics), however the seismic input parameters were selected by the NPP Kozloduy staff, Section HTS and SC (Hydro-Technical Systems and Engineering Structures). The applied methodology was developed by the Institute of Earthquake Engineering and Engineering Seismology staff. This report presents all relevant items related to the selected specimen seismic testing for seismic qualification such as: description of the tested specimen, mounting conditions on the shaking table, selection of seismic input parameters and creation of seismic excitations, description of the testing equipment, explanation of the applied methodology, 'on line' and 'off line' monitoring of the tested specimen, functioning capabilities, discussion of the results and their presentation and finally conclusions and recommendations. In this partial project report, two items are presented. The first item presents a review of the existing and used regulations for performing of the seismic and vibratory withstand testing of electro-mechanical equipment. The selection is made based on MEA, IEEE, IEC and former Soviet Union regulations. The second item presents the abstracts of all the tests performed at the Institute of Earthquake Engineering and Engineering Seismology in Skopje. The selected regulations, the experience of the Institute that has been gathered for the last seventeen years and some theoretical and experimental research will be the basis for further investigations for development of a synthesised methodology for seismic qualification of differently categorized equipment for nuclear power plants

  10. Affordable Development and Qualification Strategy for Nuclear Thermal Propulsion

    Science.gov (United States)

    Gerrish, Harold P., Jr.; Doughty, Glen E.; Bhattacharyya, Samit K.

    2013-01-01

    Nuclear Thermal Propulsion (NTP) is a concept which uses a nuclear reactor to heat a propellant to high temperatures without combustion and can achieve significantly greater specific impulse than chemical engines. NTP has been considered many times for human and cargo missions beyond low earth orbit. A lot of development and technical maturation of NTP components took place during the Rover/NERVA program of the 60's and early 70's. Other NTP programs and studies followed attempting to further mature the NTP concept and identify a champion customer willing to devote the funds and support the development schedule to a demonstration mission. Budgetary constraints require the use of an affordable development and qualification strategy that takes into account all the previous work performed on NTP to construct an existing database, and include lessons learned and past guidelines followed. Current guidelines and standards NASA uses for human rating chemical rocket engines is referenced. The long lead items for NTP development involve the fuel elements of the reactor and ground testing the engine system, subsystem, and components. Other considerations which greatly impact the development plans includes the National Space Policy, National Environmental Policy Act, Presidential Directive/National Security Council Memorandum #25 (Scientific or Technological Experiments with Possible Large-Scale Adverse Environmental Effects and Launch of Nuclear Systems into Space), and Safeguards and Security. Ground testing will utilize non-nuclear test capabilities to help down select components and subsystems before testing in a nuclear environment to save time and cost. Existing test facilities with minor modifications will be considered to the maximum extent practical. New facilities will be designed to meet minimum requirements. Engine and test facility requirements are based on the driving mission requirements with added factors of safety for better assurance and reliability

  11. Methods for qualification of highly reliable software - international procedure

    International Nuclear Information System (INIS)

    Kersken, M.

    1997-01-01

    Despite the advantages of computer-assisted safety technology, there still is some uneasyness to be observed with respect to the novel processes, resulting from absence of a body of generally accepted and uncontentious qualification guides (regulatory provisions, standards) for safety evaluation of the computer codes applied. Warranty of adequate protection of the population, operators or plant components is an essential aspect in this context, too - as it is in general with reliability and risk assessment of novel technology - so that, due to appropriate legislation still missing, there currently is a licensing risk involved in the introduction of digital safety systems. Nevertheless, there is some extent of agreement within the international community and utility operators about what standards and measures should be applied for qualification of software of relevance to plant safety. The standard IEC 880/IEC 86/ in particular, in its original version, or national documents based on this standard, are applied in all countries using or planning to install those systems. A novel supplement to this standard, document /IEC 96/, is in the process of finalization and defines the requirements to be met by modern methods of software engineering. (orig./DG) [de

  12. Qualification of the neutronic evolution of LWR fuels in MELUSINE

    International Nuclear Information System (INIS)

    Beretz, D.; Garcin, J.; Ducros, G.; Vanhumbeeck, D.; Chaucheprat, P.

    1984-09-01

    MELUSINE, a swimming pool type reactor, in Grenoble, for research and technological irradiations is well fitted to the neutronic evolution qualification of the LWR fuel. Thus, with an adjustment of the lattice pitch, representative neutron spectrum locations are available. The re-leading management and the regulation mode flexibility of MELUSINE lead to reproductible neutronic parameters configurations without restricting the reactor to this purpose only. Under these conditions, simple calculations can be carried out for interpretation, without taking into account the whole core. An instrumentation by Self Power Neutron Detectors (collectrons) gives on-line information on the fluxes at the periphery of the device. When required by the neutronicians, experimental pins can be unloaded during the irradiation process and scanned on a gammametry bench immersed in the reactor-pool itself, before their isotopic composition analysis. Thus, within the framework of neutronic evolution qualification, are studied fuel pins for advanced assemblies for the light water reactors or their derivatives, with large advantages over irradiations in power reactors [fr

  13. Teacher qualification and the achievement gap in early primary grades.

    Directory of Open Access Journals (Sweden)

    Donald Easton-Brooks

    2009-08-01

    Full Text Available Title I of the No Child Left Behind Act (P.L. 107-110, 115 Stat. 1245, 2002 holds schools accountable for reducing the academic achievement gap between the different ethnic groups and requires elementary school teachers to have at least a bachelors degree and a state certification. The purpose of this study was to examine the relationship of the qualification requirement of NCLB to the goal of reducing the academic achievement gap. The study found that students with a certified teacher for most of their early school experience scored higher in reading than students who did not have a certified teacher. In addition, certification was associated with slightly narrowing the academic gap between African American and European American students across early elementary grades.

  14. Seismic qualification method of equipment for nuclear power plant

    International Nuclear Information System (INIS)

    Kim, J.S.; Choi, T.H.; Sulaimana, R.A.

    1995-01-01

    Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying equipment for safely related service in Nuclear Power Plants in a cost effective manner

  15. A synthetic interaction screen identifies factors selectively required for proliferation and TERT transcription in p53-deficient human cancer cells.

    Directory of Open Access Journals (Sweden)

    Li Xie

    Full Text Available Numerous genetic and epigenetic alterations render cancer cells selectively dependent on specific genes and regulatory pathways, and represent potential vulnerabilities that can be therapeutically exploited. Here we describe an RNA interference (RNAi-based synthetic interaction screen to identify genes preferentially required for proliferation of p53-deficient (p53- human cancer cells. We find that compared to p53-competent (p53+ human cancer cell lines, diverse p53- human cancer cell lines are preferentially sensitive to loss of the transcription factor ETV1 and the DNA damage kinase ATR. In p53- cells, RNAi-mediated knockdown of ETV1 or ATR results in decreased expression of the telomerase catalytic subunit TERT leading to growth arrest, which can be reversed by ectopic TERT expression. Chromatin immunoprecipitation analysis reveals that ETV1 binds to a region downstream of the TERT transcriptional start-site in p53- but not p53+ cells. We find that the role of ATR is to phosphorylate and thereby stabilize ETV1. Our collective results identify a regulatory pathway involving ETV1, ATR, and TERT that is preferentially important for proliferation of diverse p53- cancer cells.

  16. The HTR modular power reactor system. Qualification of fuel elements and materials

    International Nuclear Information System (INIS)

    Heidenreich, U.; Breitling, H.; Nieder, R.; Ohly, W.; Mittenkuehler, A.; Ragoss, H.; Seehafer, H.J.; Wirtz, K.; Serafin, N.

    1989-01-01

    For further development of the HTR modular power reactor system (HTR-M-KW), the project activities for 'Qualification of fuel elements and materials' reported here cover the work for specifying the qualifications to be met by metallic and ceramic materials, taking into account the design-based requirements and the engineered safety requirements. The fission product retention data determined for the HTR modular reactor fuel elements could be better confirmed by evaluation of the experiments, and have been verified by various calculation methods for different operating conditions. The qualification of components was verified by strength analyses including a benchmark calculation for specified normal operation and emergencies; the results show a convenient behaviour of the components and their materials. In addition, a fuel element burnup measuring system was designed that applies Cs-137 gamma spectroscopy; its feasibility was checked by appropriate analyses, and qualification work is in progress. The installation of a prototype measurement system is the task for project No. 03 IAT 211. (orig.) [de

  17. Optimized qualification protocol on particle cleanliness for EUV mask infrastructure

    Science.gov (United States)

    van der Donck, J. C. J.; Stortelder, J. K.; Derksen, G. B.

    2011-11-01

    With the market introduction of the NXE:3100, Extreme Ultra Violet Lithography (EUVL) enters a new stage. Now infrastructure in the wafer fabs must be prepared for new processes and new materials. Especially the infrastructure for masks poses a challenge. Because of the absence of a pellicle reticle front sides are exceptionally vulnerable to particles. It was also shown that particles on the backside of a reticle may cause tool down time. These effects set extreme requirements to the cleanliness level of the fab infrastructure for EUV masks. The cost of EUV masks justifies the use of equipment that is qualified on particle cleanliness. Until now equipment qualification on particle cleanliness have not been carried out with statistically based qualification procedures. Since we are dealing with extreme clean equipment the number of observed particles is expected to be very low. These particle levels can only be measured by repetitively cycling a mask substrate in the equipment. Recent work in the EUV AD-tool presents data on added particles during load/unload cycles, reported as number of Particles per Reticle Pass (PRP). In the interpretation of the data, variation by deposition statistics is not taken into account. In measurements with low numbers of added particles the standard deviation in PRP number can be large. An additional issue is that particles which are added in the routing outside the equipment may have a large impact on the testing result. The number mismatch between a single handling step outside the tool and the multiple cycling in the equipment makes accuracy of measurements rather complex. The low number of expected particles, the large variation in results and the combined effect of added particles inside and outside the equipment justifies putting good effort in making a test plan. Without a proper statistical background, tests may not be suitable for proving that equipment qualifies for the limiting cleanliness levels. Other risks are that a

  18. Selection and application of C18200 chrome copper for the OHTE confinement test helical coil

    International Nuclear Information System (INIS)

    Puhn, F.A.; Graumann, D.W.

    1981-01-01

    The selection and qualification of copper for the OHTE confinement test helical coil (H-coil) was a crucial step in the success of this new experiment. Previous problems encountered at General Atomic Company with close tolerance machined parts made from high strength copper were identified. The design criteria included selecting a material with minimal warpage during machining, an electrical conductivity >80% IACS, and a yield strength of at least 241 Mpa (35 ksi). The investigation of candidate materials and testing samples led to selection of a material that fully met all requirements. The C18200 chrome copper forged plates were supplied by the Ampco Metal Division of Ampco-Pittsburgh Corporation

  19. Earthquake experience and seismic qualification by indirect methods in nuclear installations

    International Nuclear Information System (INIS)

    2003-01-01

    In recent years, many operational nuclear power plants around the world have conducted seismic re-evaluation programmes either as part of a review of seismic hazards or to comply with best international nuclear safety practices. In this connection, Member States have called on the IAEA to carry out several seismic review missions at their plants, primarily those of WWER and RBMK design. One of the critical safety issues that arose during these missions was that of seismic qualification (determination of fitness for service) of already installed plant distribution systems, equipment and components. The qualification of new components, equipment and distribution systems cannot be replicated for equipment that is already installed and operational in plants, as this process is neither feasible nor appropriate. For this reason, seismic safety experts have developed new procedures for the qualification of installed equipment: these procedures seek to demonstrate that installed equipment, through a process of comparison with new equipment, is apt for service. However, these procedures require large sets of criteria and qualification databases and call for the use of engineering judgement and experience, all of which open the door to wide margins of interpretation. In order to guarantee a sound technical basis for the qualification of in-plant equipment, currently applied to 70% to 80% of all plant equipment, the regulatory review of this type of qualification process calls for a detailed assessment of the technical procedures applied. Such an assessment is the first step towards eliminating the risk of large differences in qualification results between different plants, operators and countries, and guaranteeing the reliability of seismic re-evaluation programmes. Bearing this in mind, in 1999, the IAEA convened a seminar and technical meeting on seismic qualification under the auspices of the IAEA Technical Co-operation programme. Altogether 66 senior experts attended the

  20. Mechanical seals qualification procedure of the main pumps of nuclear power plants in France

    International Nuclear Information System (INIS)

    Buchdahl, D.; Martin, R.; Girault, J.M.

    1992-12-01

    Many important pumps in the nuclear power plants are equipped with mechanical seals. The good behaviour and reliability of mechanical seals depend specially on the quality and the stability of an interface of several microns. Peripheral speed reaches 50 m/s and pressure 5 MPa, shaft diameter may be 200 mm. Any failure of the mechanical seals may stop the production of electricity or may compromise nuclear safety. As far back as 1970, EDF has conducted qualification actions for the most important mechanical seals in terms of availability and safety. A qualification of mechanical seals needs three steps: - constructor test (tuning) at normal conditions, -qualification test on test rig at EDF/DER (semi-industrial) at normal, exceptional and incidental conditions lasting about 1500 h, - industrial qualification test in nuclear power station over one year. Several supplying sources are absolutely necessary. Any pump may receive mechanical seals from at least two different suppliers. A compromise had to be found to restrict the suppliers' number down to three. This choice concerned three high technology suppliers. A consistent modification procedure had been developed (references file procedure). For each power plant series, about ten types of mechanical seals are concerned. The selection criteria are the higher loads factors P, Vg or the safety related importance. This expensive approach is useful for EDF, many functional failures have been detected before the serial mechanical seals installation in the power plants. (authors). 1 annexe

  1. KAEC experience in development of the regulatory framework for training and qualification

    International Nuclear Information System (INIS)

    Kim, A.; Idrissova, M.; Kossilov, Al.; Pryakhin, A.

    2002-01-01

    structure should be established. In connection with the subject of our consideration their should include regulations, requirements, recommendations and guides in respect of the questions of the personnel training, qualification, examination and authorization for the right of conducting the activity in the field of atomic energy use. Those above-mentioned documents shall be established and implemented for the activities of the KAEC on regulatory control and supervision. A big variety of Kazakhstan nuclear facilities and considerable amount of personnel involved in nuclear activities in a combination with limited resources dictate outstanding need in an implementation of thought-out, balanced and systematic approach to the development and upgrade of Kazakhstan nuclear training, qualification and authorization infrastructures. These considerations were the basis for planning and implementation of the IAEA and KAEC joint activities. The 1999-2001 activities included the development of personnel-related sample regulation for Kazakhstan taking into account the needs identified under Technical Co-operation Project KAZ/9/006 'NPP Siting in Kazakhstan' TC Project. The IAEA TC Project KAZ/9/006 was implemented since 1999. One of the activities being performed by the IAEA in co-operation with the Kazakhstan Atomic Energy Committee is a support in personnel-related field. This support has a multi-aspect nature. One of the challenging factors identified was the absence of thought-out up-to-date structure of specific documents serving as a basis for regulating and supervision of such personnel-related activities as selection, training, qualification, certification/licensing and authorization of individuals involved in the activities connected with the use of atomic energy. But corresponding specific requirements for NPP personnel, their competence, qualification and authorization, for various stages of nuclear power plant life-cycle, shall ultimately correspond to the Kazakhstan legal

  2. Highlighting the gap between critical outcomes requirements and built environment education in South Africa

    CSIR Research Space (South Africa)

    Ampofo-Anti, NL

    2007-06-01

    Full Text Available This paper aims to highlight the discrepancies between current built environment education and Critical Outcomes requirements of the South African National Qualifications Framework (NQF)...

  3. Audit Committee Quality and Financial Reporting Quality: A Study of Selected Indian Companies

    Directory of Open Access Journals (Sweden)

    Kanukuntla Shankaraiah

    2017-03-01

    Full Text Available This study examines audit committee quality and its relationship with financial reporting quality. The population of this study consists of the companies listed in Bombay Stock Exchange (BSE between years 2002 and 2012. Using Godden sample size formula, 133 companies are selected randomly for the study. It is found that in most of the equity based listed companies at BSE under study have complied with the legal formalities, for instance, appointment of independent directors, number of meetings, size of the audit committee, legal qualifications and financial qualifications of the directors, as they were required for the listing at a stock exchange in India. Further, the analysis and tests state that board size, audit committee meetings and its size have relationship with the financial reporting practices, but the CEO tenure and hold, board independence, net income, proportion of independent directors on board, legal qualifications and financial qualifications of the directors and overlap of audit committee members on compensation committee, have no influence on the financial reporting practices. Thus, it may be inferred that the companies may improve the financial reporting quality, by managing the board size, audit committee meetings and size, as these characteristics have significant relationship with financial reporting quality.

  4. Development of nuclear equipment qualification technology

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

    1999-03-01

    In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

  5. Essential elements of an effective data qualification

    International Nuclear Information System (INIS)

    Jenkins, E.W.

    1994-01-01

    Before data is used in any statistical evaluation, it should be subjected to a thorough data qualification to ensure its integrity. Data Qualification efforts may vary in scope but should all contain certain basic elements. Outliers should be eliminated so that any estimates obtained from the data will not be overly biased. Plots may be generated to uncover potential outliers, and these observations can be confirmed as being anomalous through the use of statistical testing. Non-stationarity of the data (i.e., time trends) may also be initially identified through the use of plots and confirmed by the results of statistical analyses, e.g., the use of the Kendall's tau statistic. When the dataset has been qualified, replicates and duplicates should be averaged to create a pseudo-independence between data points. An algorithm based on the groundwater data from the Savannah River Site has been used by the Applied Statistics Group at Westinghouse Savannah River Company for this

  6. Equipment qualification research program: program plan

    International Nuclear Information System (INIS)

    Dong, R.G.; Smith, P.D.

    1982-01-01

    The Lawrence Livermore National Laboratory (LLNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has developed this program plan for research in equipment qualification (EQA). In this report the research program which will be executed in accordance with this plan will be referred to as the Equipment Qualification Research Program (EQRP). Covered are electrical and mechanical equipment under the conditions described in the OBJECTIVE section of this report. The EQRP has two phases; Phase I is primarily to produce early results and to develop information for Phase II. Phase I will last 18 months and consists of six projects. The first project is program management. The second project is responsible for in-depth evaluation and review of EQ issues and EQ processes. The third project is responsible for detailed planning to initiate Phase II. The remaining three projects address specific equipment; i.e., valves, electrical equipment, and a pump

  7. Here, KAPTUR This! Identifying and Selecting the Infrastructure Required to Support the Curation and Preservation of Visual Arts Research Data

    Directory of Open Access Journals (Sweden)

    Leigh Garrett

    2013-11-01

    Full Text Available Research data is increasingly perceived as a valuable resource and, with appropriate curation and preservation, it has much to offer learning, teaching, research, knowledge transfer and consultancy activities in the visual arts. However, very little is known about the curation and preservation of this data: none of the specialist arts institutions have research data management policies or infrastructure and anecdotal evidence suggests that practice is ad hoc, left to individual researchers and teams with little support or guidance. In addition, the curation and preservation of such diverse and complex digital resources as found in the visual arts is, in itself, challenging. Led by the Visual Arts Data Service, a research centre of the University for the Creative Arts, in collaboration with the Glasgow School of Art; Goldsmiths College, University of London; and University of the Arts London, and funded by JISC, the KAPTUR project (2011-2013 seeks to address the lack of awareness and explore the potential of research data management systems in the arts by discovering the nature of research data in the visual arts, investigating the current state of research data management, developing a model of best practice applicable to both specialist arts institutions and arts departments in multidisciplinary institutions, and by applying, testing and piloting the model with the four institutional partners. Utilising the findings of the KAPTUR user requirement and technical review, this paper will outline the method and selection of an appropriate research data management system for the visual arts and the issues the team encountered along the way.

  8. Experimental qualification of nuclear components

    Energy Technology Data Exchange (ETDEWEB)

    Alliot, P; Fronte, T; Genty, F [FRAMATOME - Cedex 16, Paris la Defense (France)

    1988-07-01

    In the process of showing the adequacy of the seismic design of French PWR reactor, Fermat has repeatedly used dynamic testing on actual nuclear reactor components both on site and in manufacturing shops. The objective and results of a few representative examples of this on-site experimental verification are presented in this paper: the experimental dynamic analysis of a manipulator crane; the investigation of the seismic behaviour of fuel storage racks equipped with aseismic bearing devices. Difficulties to select satisfactory testing methods are also discussed for the particular case of the electrical cabinets. (author)

  9. Experimental qualification of nuclear components

    International Nuclear Information System (INIS)

    Alliot, P.; Fronte, T.; Genty, F.

    1988-01-01

    In the process of showing the adequacy of the seismic design of French PWR reactor, Fermat has repeatedly used dynamic testing on actual nuclear reactor components both on site and in manufacturing shops. The objective and results of a few representative examples of this on-site experimental verification are presented in this paper: the experimental dynamic analysis of a manipulator crane; the investigation of the seismic behaviour of fuel storage racks equipped with aseismic bearing devices. Difficulties to select satisfactory testing methods are also discussed for the particular case of the electrical cabinets. (author)

  10. High Temperature Materials Interim Data Qualification Report

    International Nuclear Information System (INIS)

    Lybeck, Nancy

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: (1) Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing - 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. (2) Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram - 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

  11. The DWPF waste form qualification program

    International Nuclear Information System (INIS)

    Marra, S.L.; Plodinec, M.J.

    1994-01-01

    Prior to the introduction of radioactive feed into the Defense Waste Processing Facility for immobilization in borosilicate glass an extensive waste qualification program must be completed. The DWPF must demonstrate its ability to comply with the Waste Acceptance Product Specifications. This ability is being demonstrated through laboratory and pilot scale work and will be completed after the full operation of the DWPF using various simulated feeds

  12. Problems and Tasks of TRAINING at Courses for Enhancement of Qualification in the Radioactive Waste Management Area

    International Nuclear Information System (INIS)

    Sobolev, I. A.; Dmitriev, S. A.; Batyukhnova, O. G.; Shcherbatova, T. D.; Ojovan, M. I.; Arustamov, A. E.

    2002-01-01

    Requirements to the professional competence of the personnel engaged in the area of the radioactive waste management are increased. Higher school cannot supply the branch with the qualified personnel; therefore special attention should be given to the system of staff retraining and to the increase of their qualification. In that paper the analysis of SIA ''Radon'' experience on the organization and carrying out training at courses of qualification improvement is represented. The main criterion of the analysis is the research of an education efficiency. Also here the basic directions of the training process improving are submitted as well as the requirements that should be considered when forming the teaching staff and trainees groups

  13. Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel. That is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

  14. Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel; that is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

  15. Qualification standard for photovoltaic concentrator modules

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, R.; Kurtz, S.; Bottenberg, W. R.; Hammond, R.; Jochums, S. W.; McDanal, A. J.; Roubideaux, D.; Whitaker, C.; Wohlgemuth, J.

    2000-05-05

    The paper describes a proposed qualification standard for photovoltaic concentrator modules. The standard's purpose is to provide stress tests and procedures to identify any component weakness in photovoltaic concentrator modules intended for power generation applications. If no weaknesses are identified during qualification, both the manufacturer and the customer can expect a more reliable product. The qualification test program for the standard includes thermal cycles, humidity-freeze cycles, water spray, off-axis beam damage, hail impact, hot-spot endurance, as well as electrical tests for performance, ground continuity, isolation, wet insulation resistance, and bypass diodes. Because concentrator module performance can not be verified using solar simulator and reference cell procedures suitable for flat-plate modules, the standard specifies an outdoor I-V test analysis allowing a performance comparison before and after a test procedure. Two options to this complex analysis are the use of a reference concentrator module for side-by-side outdoor comparison with modules undergoing various tests and a dark I-V performance check.

  16. Qualifications and training of staff of the regulatory body for nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Agency's Safety Series No.50-C-G, entitled ''Governmental Organization for the Regulation of Nuclear Power Plants: A Code of Practice'', and is mainly concerned with the qualifications and training requirements of the staff of bodies regulating nuclear power plants. It is not concerned with staff for regulating other phases of the fuel cycle, such as fuel fabrication and management. This Guide provides recommendations and guidance for establishing the qualifications required for the staff of the regulatory body. These requirements include academic training, work experience and other abilities. It also establishes the training programmes and activities necessary for personnel within the regulatory body

  17. Development and Qualification of an Antenna Pointing Mechanism for the ExoMars High-Gain Antenna

    Science.gov (United States)

    St-Andre, Stephane; Dumais, Marie-Christine; Lebel, Louis-Philippe; Langevin, Jean-Paul; Horth, Richard; Winton, Alistair; Lebleu, Denis

    2015-09-01

    actuator’s auxiliary shaft through a tuned stiffness flex coupling.• Restriction for Electrical Power to Rotary Actuator: Each actuator is powered with less than 7 Watts. The maximum speed of the system is 0.5 deg/sec and it provides the required margin as per ECSS Requirements.The qualification tests, which have been performed successfully in 2014, have shown that the chosen solution is suitable for the ExoMars mission. The environment testing (vibration, shock, TVAC) and its life test over 120 days in TVAC were especially stringent. The new design passed the required 5.9 M output degrees of rotation without noticeable functionality degradation on components. The actuator drive axis stiffness shows a decrease after its life (≈-40 %), but the results were expected and within ExoMars requirements.The paper will present many lessons learned such as MGSE difficulties during the qualification test campaign, design choices to minimize the mechanism overall volume, packaging of different components and selection of the sine/cosine command profile to achieve a greater life on the mechanismAs of July 2015, the High Gain Antenna Assembly (HGA-A) has been integrated to the spacecraft for S/C level testing, and RF, Shock, Vibration, and EMC testing was successfully conducted.The ExoMars TGO High Gain Antenna Assembly Contract was carried out under a program of and funded by the European Space Agency.

  18. Admission Requirements to Canadian Faculties of Medicine and Their Selection Policies = Conditions d'Admission aux Facultes de Medecine Canadiennes et Leurs Politiques de Selection.

    Science.gov (United States)

    Association of Canadian Medical Colleges, Ottawa (Ontario).

    Information is presented to help applicants to Canadian medical colleges realistically assess their chances for gaining admission. The guide is also intended for career counselors in high schools and higher education. One section provides statistics on the following characteristics that are associated with being selected: sex, age, Medical College…

  19. Team Formation under Normal versus Crisis Situations: Leaders' Assessments of Task Requirements and Selection of Team Members

    National Research Council Canada - National Science Library

    Baltos, Georgios; Mitsopoulou, Zoi

    2007-01-01

    ... with, and reliability of candidate team members. Motivation, professional capabilities, and leadership skills are the most preferred selection variables when the organizational situation is perceived as a crisis.

  20. Romanian-Canadian joint program for qualification of FCN as a CANDU fuel supplier

    International Nuclear Information System (INIS)

    Galeriu, C.A.; Andrei, G.; Bailescu, A.

    1995-01-01

    RENEL (Romania Power Authority), the co-ordinator of Romanian Nuclear Program, have decided to improve, starting 1990 the existing capability to produce CANDU nuclear fuel at FCN Pitesti. The objective of the program was defined with AAC (AECL - ANSALDO Consortium) for the qualification of FCN fuel plant according to Canadian Z299.2 standard. The Qualification Program was performed under AAC Work Order C-003. The co-ordination was assumed by AECL, as overall Design Authority. ZPI (Zircatec Precision Industries Inc., Canada), were designated to supply technical assistance, equipments and know how where necessary. After a preliminary verification of the FCN fuel plant, including the processes and system investigation, performed under AECL and ZPI assistance, the Qualification Program was defined in all details. The upgrading of documentation on all aspects required by Z299.2 was performed. Few processes needed to be reconsidered and equipment was delivered by ZPI or other suppliers. This includes mainly welding equipments and special inspection equipments. Health Physics was practically fully reconsidered. New equipment and practice were adapted to provide adequate control on health conditions. Every manufacturing and inspection process was checked to determine their performance during a Qualification Run based on acceptance criteria which have been established in the Qualification Plan. Manufacturing Demonstration Run was an important step to prove that all plant functions have been accomplished during the fabrication of 200 fuel bundles. These bundles have been fully accepted and 66 of them have been loaded in the first charge of Unit 1 Cemavoda NPS. The surveillance and audit actions made by AECL and ZPI during this period confirmed the FCN capability to operate an adequate system meeting the to required quality assurance standard. The very open attitude of AECL, Zircatec and FCN staff have stimulated the progress of the project and a successful achievement of the

  1. A uniform approach for on-site training and qualification of health physics technicians

    International Nuclear Information System (INIS)

    Till, J.E.

    1977-01-01

    Estimates show that in the U.S. approx. 75% of the health physics technicians received their training through courses offered by their employer. The quality and the extent of this training vary considerably among nuclear facilities. This paper describes a uniform approach for on-site training and qualification of health physics technicians applicable to all nuclear facilities. The program consists of four levels of qualification: Health Physics Technician Trainee, Technician I, Technician II and Senior Technician. The training is divided into modules that are composed of formal lectures, practical factors, experience, and a comprehensive examination. The minimum time required from hiring of inexperienced trainees to qualification as Senior Technicians is approx. 24 months. A qualification guide lists each step a technician must complete in the training program and provides documentation which facilitates audits by internal and external groups. Although items in the program would differ between facilities, the program provides specific titles for technicians, based on their training and experience, which would be applicable throughout the nuclear industry. (author)

  2. Re-qualification of MTR-type fuel plates fabrication process

    International Nuclear Information System (INIS)

    Elseaidy, I.M.; Ghoneim, M.M.

    2010-01-01

    The fabricability issues with increased uranium loading due to use low enrichment of uranium (LEU), i.e. less than 20 % of U 235 , increase the problems which occur during compact manufacturing, roll bonding of the fuel plates, potential difficulty in forming during rolling process, mechanical integrity of the core during fabrication, potential difficulty in meat homogeneity, and the ability to fabricate plates with thicker core as a means of increasing total uranium loading. To produce MTR- type fuel plates with high uranium loading (HUL) and keep the required quality of these plates, many of qualification process must be done in the commissioning step of fuel fabrication plant. After that any changing of the fabrication parameters, for example changing of any of the raw materials, devises, operators, and etc., a re- qualification process should be done in order to keep the quality of produced plates. Objective of the present work is the general description of the activities to be accomplished for re-qualification of manufacturing MTR- type nuclear fuel plates. For each process to be re-qualified, a detailed of re-qualification process were established. (author)

  3. Prognostics-based qualification of high-power white LEDs using Lévy process approach

    Science.gov (United States)

    Yung, Kam-Chuen; Sun, Bo; Jiang, Xiaopeng

    2017-01-01

    Due to their versatility in a variety of applications and the growing market demand, high-power white light-emitting diodes (LEDs) have attracted considerable attention. Reliability qualification testing is an essential part of the product development process to ensure the reliability of a new LED product before its release. However, the widely used IES-TM-21 method does not provide comprehensive reliability information. For more accurate and effective qualification, this paper presents a novel method based on prognostics techniques. Prognostics is an engineering technology predicting the future reliability or determining the remaining useful lifetime (RUL) of a product by assessing the extent of deviation or degradation from its expected normal operating conditions. A Lévy subordinator of a mixed Gamma and compound Poisson process is used to describe the actual degradation process of LEDs characterized by random sporadic small jumps of degradation degree, and the reliability function is derived for qualification with different distribution forms of jump sizes. The IES LM-80 test results reported by different LED vendors are used to develop and validate the qualification methodology. This study will be helpful for LED manufacturers to reduce the total test time and cost required to qualify the reliability of an LED product.

  4. Qualification Approach for the CMC Nose Cap of X-38

    Science.gov (United States)

    Weihs, H.; Gülhan, A.

    2002-01-01

    In October 2001 the flight hardware of the TPS nose assembly of X-38 has been installed at the main structure of the X-38 V201 vehicle at NASA's Johnson Space Center, Houston Texas. X-38 is a test vehicle for the planned Crew Return Vehicle CRV for the International Space Station ISS. Currently the flight of the X-38 is scheduled for 2005. Besides the Body flaps (MAN-T) and the nose skirt system (ASTRIUM, MAN-T) the nose cap system is one of the essential hot structure components that were developed within Germany's national TETRA (Technologies for future space transportation systems) programme. The integration of the hardware was an important milestone for the nose cap development which started approx. 5 years ago. DLR-Stuttgart is responsible for the design and manufacturing of the CMC based nose cap system, which has to withstand the extreme thermal loads during re-entry which will induce a maximum temperature up to 1750 °C on the surface of the cap. Thus, the shell of the cap system is designed and manufactured using DLR's C/C-SiC material which is a special kind of carbon based ceramic matrix composite (CMC) material produced via the in house liquid silicon infiltration process of DLR. This material has demonstrated its good temperature resistance during FOTON and EXPRESS re-entry capsule missions. Besides the design and manufacturing of the nose cap system, the qualification approach was an important effort of the development work. Missing a test facility which is able to simulate all loading conditions from lift off to re-entry and landing, is was necessary to separate the loads and to use different test facilities. Considering the limitations of the facilities, the budget and time constraints, an optimized test philosophy has been established. The goal was to use a full scale qualification unit including all TPS components of the nose area for most of the tests. These were the simulation of ascent loads given by the shuttle requirements and descent loads

  5. Actively cooled plasma facing components qualification, commissioning and health monitoring

    International Nuclear Information System (INIS)

    Escourbiac, F.; Durocher, A.; Grosman, A.; Courtois, X.; Farjon, J.-L.; Schlosser, J.; Merola, M.; Tivey, R.

    2006-01-01

    In modern steady state magnetic fusion devices, actively cooled plasma facing components (PFC) have to handle heat fluxes in the range of 10-20 MW/m 2 . This generates a number of engineering constraints: the armour materials must be refractory and compatible with plasma wall interaction requirements (low sputtering and/or low atomic number); the heat sink must offer high thermal conductivity, high mechanical resistance and sufficient ductility; the component cooling system -which is generally based on the circulation of pressurized water in the PFC's heat sink - must offer high thermal heat transfer efficiency. Furthermore, the assembling of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on thermo-mechanical properties of materials and design requirements. Life time of the PFC during plasma operation are linked to their manufacturing quality, in particular they are reduced by the possible presence of flaw assembling. The fabrication of PFC in an industrial frame including their qualification and their commissioning - which consists in checking the manufacturing quality during and at the end of manufacture - is a real challenge. From experience gained at Tore Supra on carbon fibre composite flat tiles technology components, it was assessed that a set of qualifications activities must be operated during R(and)D and manufacturing phases. Dedicated Non Destructive Technique (NDT) based on advanced active infrared thermography was developed for this purpose, afterwards, correlations between NDT, high heat flux testing and thermomechanical modelling were performed to analyse damage detection and propagation, and define an acceptance criteria valuable for industrial application. Health monitoring using lock-in technique was also recently operated in-situ of the Tore Supra tokamak for detection of possible defect propagation during operations, presence of acoustic precursor for critical heat flux detection induced

  6. Design and qualification testing of a strontium-90 fluoride heat source

    International Nuclear Information System (INIS)

    Fullam, H.T.

    1981-12-01

    The Strontium Heat Source Development Program began at the Pacific Northwest Laboratory (PNL) in 1972 and is scheduled to be completed by the end of FY-1981. The program is currently funded by the US Department of Energy (DOE) By-Product Utilization Program. The primary objective of the program has been to develop the data and technology required to permit the licensing of power systems for terrestrial applications that utilize 90 SrF 2 -fueled radioisotope heat sources. A secondary objective of the program has been to design and qualification-test a general purpose 90 SrF 2 -fueled heat source. The effort expended in the design and testing of the heat source is described. Detailed information is included on: heat source design, licensing requirements, and qualification test requirements; the qualification test procedures; and the fabrication and testing of capsules of various materials. The results obtained in the qualification tests show that the outer capsule design proposed for the 90 SrF 2 heat source is capable of meeting current licensing requirements when Hastelloy S is used as the outer capsule material. The data also indicate that an outer capsule of Hastelloy C-4 would probably also meet licensing requirements, although Hastelloy S is the preferred material. Therefore, based on the results of this study, the general purpose 90 SrF 2 heat source will consist of a standard WESF Hastelloy C-276 inner capsule filled with 90 SrF 2 and a Hastelloy S outer capsule having a 2.375-in. inner diameter and 0.500-in. wall thickness. The end closures for this study, the general purpose 90 SrF 2 heat a Hastelloy S outer capsule having a 2.375-in. inner diameter and 0.500-in. wall thickness. The end closures for the outer capsule will utilize an interlocking joint design requiring a 0.1-in. penetration closure weld

  7. Computer code qualification program for the Advanced CANDU Reactor

    International Nuclear Information System (INIS)

    Popov, N.K.; Wren, D.J.; Snell, V.G.; White, A.J.; Boczar, P.G.

    2003-01-01

    Atomic Energy of Canada Ltd (AECL) has developed and implemented a Software Quality Assurance program (SQA) to ensure that its analytical, scientific and design computer codes meet the required standards for software used in safety analyses. This paper provides an overview of the computer programs used in Advanced CANDU Reactor (ACR) safety analysis, and assessment of their applicability in the safety analyses of the ACR design. An outline of the incremental validation program, and an overview of the experimental program in support of the code validation are also presented. An outline of the SQA program used to qualify these computer codes is also briefly presented. To provide context to the differences in the SQA with respect to current CANDUs, the paper also provides an overview of the ACR design features that have an impact on the computer code qualification. (author)

  8. Power/response spectrum transformations in equipment qualification

    International Nuclear Information System (INIS)

    Unruh, J.F.; Kana, D.D.

    1985-01-01

    Since its introduction a few years ago the use of the power/response spectrum transformation has gained considerable interest and acceptance, and a number of new applications of the transformation have been developed in the equipment qualification area. A brief review of the power/response spectrum transformation is given with a discussion of the input/output relationships for linear systems required for elevated power spectrum generation. Frequency content of earthquakelike signals is discussed with emphasis on the resolution given by the PSD. The problem of excessive ZPA due to inconsistent spectra enveloping and mechanical nonlinearities is also discussed. The PSD/RS transformation is applied to the problems of combining various dynamic load events, developing bounding spectra, and developing damping consistent test spectra. Development of elevated component spectra corrected for base overtest and generation from in-situ measurements is reviewed

  9. Training and qualification program for nuclear criticality safety technical staff

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1996-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. The program is compliant with requirements and provides evidence that a systematic approach has been taken to indoctrinate new technical staff. Development involved task analysis to determine activities where training was necessary and the standard which must be attained to qualify. Structured mentoring is used where experienced personnel interact with candidates using checksheets to guide candidates through various steps and to provide evidence that steps have been accomplished. Credit can be taken for the previous experience of personnel by means of evaluation boards which can credit or modify checksheet steps. Considering just the wealth of business practice and site specific information a new person at a facility needs to assimilate, the program has been effective in indoctrinating new technical staff personnel and integrating them into a productive role. The program includes continuing training

  10. The qualification of a new fuel - the operator's perspective

    International Nuclear Information System (INIS)

    Koonen, E.

    2001-01-01

    Operators of a research reactor generally have as their primary mission to provide the users with a safe, reliable and economic source of neutrons. They have to assure the availability of that source, while respecting the requirements of the license. The fuel management is one of the major aspects they have to tackle in order to fulfill their mission. This sometimes includes the qualification of a new fuel and the core conversion. The operator has to assure that the whole process is conducted in such manner that the availability of the neutron source is only minimally disturbed, that the costs are kept under control and the characteristics of the neutron source are preserved. This paper gives an overview of the various issues that the operator has to consider. (author)

  11. Infrared LED Array For Silicon Strip Detector Qualification

    CERN Document Server

    Dirkes, Guido; Hartmann, Frank; Heier, Stefan; Schwerdtfeger, Wolfgang; Waldschmitt, M; Weiler, K W; Weseler, Siegfried

    2003-01-01

    The enormous amount of silicon strip detector modules for the CMS tracker requires a test-sytem to allow qualification of each individual detector module and its front-end electronics within minutes. The objective is to test the detector with a physical signal. Signals are generated in the detector by illumination with lightpulses emitted by a LED at 950~nm and with a rise time of 10~ns. In order to avoid a detector moving, an array of 64 LEDs is used, overlaping the complete detector width. The total length of an array is 15~cm. The spot size of an individual LED is controlled by apertures to illuminate about 25 strips. Furthermore it is possible to simulate the high leakage current of irradiated sensors by constant illumination of the sensor. This provides an effective mean to identfy pinholes on a sensor.

  12. QUALIFICATIONS FRAMEWORKS FOR LIFELONG LEARNING CONQUERING THE WORLD?

    Directory of Open Access Journals (Sweden)

    Arjen Deij

    2014-01-01

    Full Text Available The paper reveals the international prospects of developing and spreading the qualifications frameworks across the globe. It introduces the key terms and concepts related to the given issue, and examines both the benefits and challenges of qualifications frameworks implementation. The author looks into the origins and causes of the worldwide interest in qualifications framework application, and gives the overview of related recent publications and their conclusions to reinforce the provided argumentation.

  13. On relaxing the Mangasarian-Fromovitz constraint qualification

    Czech Academy of Sciences Publication Activity Database

    Kruger, A.Y.; Minchenko, L.; Outrata, Jiří

    2014-01-01

    Roč. 18, č. 1 (2014), s. 171-189 ISSN 1385-1292 R&D Projects: GA ČR GAP402/12/1309 Institutional support: RVO:67985556 Keywords : Nonlinear programming * Regularity conditions * Constraint qualifications * Lagrange multipliers * Mangasarian–Fromovitz constraint qualification * Constant rank constraint qualification Subject RIV: BA - General Mathematics Impact factor: 0.679, year: 2014 http://library.utia.cas.cz/separaty/2014/MTR/outrata-0426110.pdf

  14. SRNL Phase 1 Assessment Of The WAC/DQO And Unit Operations For The WTP Waste Qualification Program

    International Nuclear Information System (INIS)

    Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

    2012-01-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification

  15. SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

    2012-05-16

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap

  16. Seismic qualification testing at the National Engineering Laboratory

    International Nuclear Information System (INIS)

    Fairbairn, J.

    1984-01-01

    Servohydraulic shaker tables have been developed for the simulation of vibration environments including earthquakes. The use of these facilities for seismic qualification of nuclear equipment is described. (author)

  17. 77 FR 10607 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-02-22

    ...-2011-0367] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce. The...). [[Page 10608

  18. DATA QUALIFICATION REPORT: MAJOR ION AND PH DATA FOR USE ON THE YUCCA MOUNTAIN PROJECT

    International Nuclear Information System (INIS)

    C. WILSON; D.M. JENKINS; T. STEINBORN; R. WEMHEUER

    2000-01-01

    This data qualification report uses technical assessment and corroborating data methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', to qualify major ion and pH data. This report was prepared in accordance with Data Qualification Plan TDP-NBS-GS-00003 1, Revision 2. Additional reports will be prepared to address isotopic and precipitation-related data. Most of the data considered in this report were acquired and developed by the U.S. Geological Survey (USGS). The data qualification team considers the sampling and analytical protocols employed by the USGS over the time period of data acquisition to be state-of-the-art. The sample collection methodologies have evolved with no significant change that could affect the quality of the data considered in this report into the currently used Hydrologic Procedures that support the Yucca Mountain Project-approved USGS Quality Assurance Program Plan. Consequently, for USGS data, the data collection methods, documentation, and results are reasonable and appropriate in view of standard practice at the time the data were collected. A small number of data sets were collected by organizations other than the USGS and were reviewed along with the other major ion and pH data using corroborating data methods. Hydrochemical studies reviewed in this qualification report indicate that the extent and quality of corroborating data are sufficient to support qualification of both USGS and non-USGS major ion and pH data for generalized hydrochemical studies. The corroborating data included other major ion and pH data, isotope data, and independent hydrological data. Additionally, the analytical adequacy of the major ion data was supported by a study of anion-cation charge balances. Charge balance errors for USGS and non-USGS data were under 10% and acceptable for all data. This qualification report addresses the specific major ion data sets

  19. Selection and assessment of contractors; Auswahl und Beurteilung von Auftragnehmerfirmen

    Energy Technology Data Exchange (ETDEWEB)

    Lier, K.H. [ExxonMobil Production Deutschland GmbH, Hannover (Germany)

    2007-09-13

    Reliable and efficient contractors are important for the activities of ExxonMobil. Qualification of contractors is to ensure that contractors provide technical services in accordance with the specifications of ExxonMobil. Apart from the financial, oranisational and legal qualification this covers technical qualification, i.e. industrial safety, health protection and environmental protection, as well as technical efficiency and quality. The ultimate intention is to find out if contractors have the processes and systems at their disposal that are required for the services. The qualification process is described. (orig.)

  20. Determination of the approximate number of welding qualification procedures, according to the AD-HP 2/1 and NUCLEN rules

    International Nuclear Information System (INIS)

    Couto, J.G.V.

    1986-01-01

    The simple equations based on the phylosophy of AD-HP 2/1 which determine the approximate number welding qualification procedures for the manufacture either of one component, or several components requested simultaneously are presented. It is also intended to help the manufacturer in the rational preparation of scheduling the required minimum qualifications for performing the work, including giving him an idea about the involved costs which the firm will have to bear in this phase prior to manufacturing. (Author) [pt